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| | 2830082850 PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 JOHN S. KEMPER VICE |
| | ...... . ...-PR ESI D E NT DEC 221983 Mr. Thomas E. Marley, Director United States Nuclear Regulatory Commission Office of Inspection and Enforcement, Region I 631 Park Avenue King of Prussia, PA 19406 |
| | |
| | ==Subject:== |
| | Significant Deficiency Report #120 Interim Report on Paul Munroe Electro-hydraulic Valve Actuators Deficiency Limerick Generating Station, Units 1 & 2 NRC Construction Permit Nos. CPPR 106 & 107 Ref erence : Telecon record J.P. Evans /R.B. Atkinson PECO-QA to Walter Baunack, USNRC dated 11/22/83 File: QUAL 2-10-2 (SDR #120) ,. |
| | |
| | ==Dear Mr. Murley:== |
| | |
| | This is an interim report regarding a significant deficiency on Electro-Hydraulic HVAC valve actuators supplied by Paul Munroe Hydraulics, Inc. to Limerick Generating Station. |
| | The Limerick Generating Station has twenty eight (28) HVAC valve operators manufactured by Paul Munroe Hydraulics, Inc. Unit 1 and Common have eighteen (18) valve operators and Unit 2 has ten (10) valve operators. |
| | Bechtel Non-Conformance Report 6866 documented the deficiencies such a.s damaged hardmre, deformed gaskets and leakage of hydraulic fluid from drain plugs at the bottom of reservoirs and from the bottom of the hydraulic manif old . Analysis of hydraulic fluid revealed that oil was heavily contaminated and did not meet the cleanliness requirement of NAS 1638, Class 6. The contaminated oil caused a varying degree of damage to most of the major components of the actuators thus requiring complete overhaul of these actuators. |
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| | 8401260303 831222 PDR ADOCK 05000352 Vf S~ PDR _ |
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| | r-dF e 2830082850 m |
| | MR. Thomas E. Murley, Director United States Nuclear Regulatory Commission Page 2 In our opinion leakage of hydraulic fluid from drain plugs at the bottom of reservoirs would have resulted in improper operation of the actuator in normal operation, since the actuator is driven by hydraulic fluid f rom the pump. Leakage of hydraulic fluid could also result in seizure of pumps. Sufficient oil may not be pumped into the accumulator because of low level of oil, thereby hydraulic energy will not be stored , |
| | in the accumulator. The pressure in the accumulator will also change due to leakage of hydraulic fluid. The hydraulic fluid stored in the accumulator may not be sufficient to move the actuator through 90 degree ro ta tion. The damage to critical components of actuators such as pumps, solenoid valves, and Flo-Torks due to contamination of hydraulic fluid and leakage of oil could have an adverse ef fect on the safe operation of the plant if it had gone uncorrected. |
| | The eighteen (18) Unit 1 and Ccmmon actuators were sent back to Paul Munroe f or disassembly, inspection, scheduled elastomer replacements and repair of damaged hardware. The inspection of the disassembled components at Paul Munroe revealed various component def ects which were apparently caused by contaminated hydraulic fluid. All eighteen (18) actuators were completelf overhauled. Critical components such as pumps, solenoid control valves, accumulators, Flo-Torks , reservoirs, and filters were replaced or repaired. The reservoirs were filled with clean Fyrquel-EHC hydraulic fluid and all actuators were f unctionally tested. The oil samples were analysed and certified to meet the cleanliness requirements of NAS 1638 Class 6. Design of the drain connection at the bottom of the reservoir was upgraded to prevent oil leakage. Larger capacity filters were installed to increase the filtration capacity. |
| | Proper operation of Unit 1 systems containing the subject valves will be verified during pre-operational activities. The Fyrquel-EHC hydraulic fluid will be sampled at the manufacturer's recommended frequencies to confirm continued cleanliness of the fluid. Unit 2 actuators will also be shipped back to the vendor for overhaul. No date has been set for this activity pending resolution of Unit 2 status. |
| | A final report will be filed with the NRC in nine (9) months from this da te. |
| | Sincerely, WSS/GMM/831222 Copy to: Director of Inspection and Enforcemen United States Nuclear Regulatory Commission Washington, DC 20555 S.K. Chaudhary, Resident NRC Inspector (Limerick)}} |
Latest revision as of 05:06, 16 April 2020
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20198Q6961998-01-12012 January 1998 Part 21 Rept Re Failed Operation of Agastat EGPI004 Relay on 971129,as Reported by Limerick Station.Caused by Insufficient Soldering.Will Notify Customers Who Purchased EPI004 & ETR14XXX004 Relays During June 1996 ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced ML20006A7141990-01-19019 January 1990 Updated Final Significant Deficiency Rept 107 Re Defective Agastat GP Relays.Initially Reported on 831129.Use of Subj Relays Does Not Represent Safety Concern & Not Reportable as Operational Concern.Test Program Developed ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20245G0411989-08-0808 August 1989 Advises That Corrective Actions for Significant Deficiency & Part 21 Rept Re Unqualified Nupro Valve Seals Completed & Resolved,Per 890707 Rept.Only 98 Nupro Test Valves Furnished on GE Racks & Addl 17 Valves Provided for Other Racks ML20246J6411989-07-0707 July 1989 Supplemental Part 21 & Deficiency Rept L2-89-44 Re Nupro Test Valves,Installed on Instrument Line Racks Furnished by Ge,Not Remaining Leak Tight During DBA Conditions.Initially Reported on 890608.Root Cause Analysis Will Be Performed ML20245K9061989-06-30030 June 1989 Significant Deficiency Repts L2-89-08,38,43 & 45-48 Re Safe Shutdown Analysis.Corrective Actions Completed & Significant Deficiencies Considered Resolved ML20244A5101989-06-0707 June 1989 Final Significant Deficiency Rept SDR-L2-89-39 Re Failure of Stainless Steel Midlock Ferrules.Caused by Isolated Stress Corrosion Cracking Not Affecting Other Penetration Ferrules in Penetration 20JX222 Replaced ML20247Q7341989-05-31031 May 1989 Significant Deficiency Rept L2-89-34 Re Tavis Pressure Differential Transmitters Installed W/O Connecting Internal Heaters.Initially Reported on 890418.Heaters Will Be Connected on All Tavis Pressure Differential Transmitters ML20247N7731989-05-31031 May 1989 Supplemental Significant Deficiency Rept Re Safe Shutdown Analysis self-assessment ML20246F9051989-05-15015 May 1989 Significant Deficiency Rept L2-89-23 Re Essential Equipment Located in Unanalyzed Environ.Installation of Conduit Seals or Reorientation of Conduit Runs Planned to Avoid Moisture Intrusion Into Electrical Equipment Prior to Startup ML20246M3681989-05-0808 May 1989 Significant Deficiency Rept L2-89-06 Re Unavailability of Suppression Pool Indication Due to App R Fire.Caused by Design Error Resulting from Lack of Procedural Guidance. Reportability Evaluation Initiated ML20248F6101989-04-13013 April 1989 Interim Significant Deficiency Rept L2-88-11 Re Inadequate Degraded Grid Undervoltage Relay Setpoints.Event Discussed W/Engineer Involved to Ensure Procedural Adherence & New Undervoltage Relays Will Be Installed ML20248F3571989-04-0303 April 1989 Interim Significant Deficiency Rept SDR-L2-89-17 Re Unavailability of Feedwater Maint Isolation Valve to Support RCIC Operation in Event of App R Fire.Initially Reported on 890303.Cause Under Investigation.Rept to Be Submitted ML20248F9451989-03-28028 March 1989 Part 21 Rept Re Replacement of Circuit Boards for Safeguard Battery Chargers.Initially Reported on 890323.C&D Power Sys Provided Instructions to Change Out 600 Ohm Fixed Resistor w/500 Ohm Variable Resistor in Charger Circuitry ML20246H0951989-03-10010 March 1989 Significant Deficiency Rept L2-88-10 Re Improper Installation of Temporary Support Brackets in safety-related 4 Kv Switchgear.Support Brackets Removed from Switchgear Cubicle Prior to Startup & Procedures Revised ML20235F8601989-02-17017 February 1989 Interim Significant Deficiency Repts SDR-L2-89-03,04 & 05 Re Unavailability of HPCI & RCIC Sys Due to App R Fire. Initially Reported on 890117.Corrective Actions Under Review & Will Be Reported by 890531 ML20196B8281988-12-0202 December 1988 Final Significant Deficiency Rept 250-2 Re Use of Insulated Wire by Westinghouse in safety-related Motor Starters. Initially Reported on 881020.Defective Components Reworked & Corrected.Action to Prevent Recurrence Not Necessary ML20206C1571988-11-0404 November 1988 Interim Deficiency Rept 249-2 Re Nonavailability of Safe Shutdown Capabilities from Outside Control Room in Event of Fire.Initially Reported on 881006.Design Change Will Be Performed.Root Cause of Condition Still Under Evaluation ML20154Q4541988-09-28028 September 1988 Final Significant Deficiency Repts 230-2 & 231-2 Re Failures of Aluminum Vertical Bus & Belleville Washers in Cutler-Hammer Motor Control Ctrs.Aluminum Vertical Bus Replaced W/Tin Plated Copper Bus ML20153B6841988-08-25025 August 1988 Final Significant Deficiency Rept 238-2 Re Use of 600 Volt Type Thhn,Thwn or Thw Wire in 120 Volt Ac Convenience Receptacles & Lighting Circuits for Control Panels.Initially Reported on 880729.Panels,load Ctrs & Switchgear Inspected ML20151F3321988-07-0808 July 1988 Interim Significant Deficiency Rept 219-2 Re Discrepancies in Pgcc Wiring.Approx 130 Addl Minor Errors Out of 10,000 Terminations Discovered During Reinsp.Final Rept Will Be Submitted by 880815 ML20195B7641988-06-15015 June 1988 Final Deficiency Rept 232-2 Re Westinghouse Type Ds Fused Disconnect Switch.Initially Reported on 880415.Mechanical Connectors Integral to Fuse Mounting Assembly Would Not Adequately Secure Some 8 Awg Wires ML20155C3401988-06-0606 June 1988 Significant Deficiency Rept 137-2 Re Potentially Defective Type Hma Auxiliary Relays.Ge Notification Per 10CFR21 Encl. Potentially Defective Equipment Inspected & Corrected Per Field Disposition Instructions from GE ML20154E6561988-05-13013 May 1988 Interim Deficiency Rept Re Use of Mechanical Cable Connectors on Westinghouse Type Ds Fused Disconnect Switches.Initially Reported on 880415.Determination of Extent That Both Wires Terminated W/Connectors Underway ML20154E6381988-05-13013 May 1988 Interim Deficiency Rept Re Aluminum Vertical Bus Failures in Cutler Hammer Motor Control Ctr.Initially Reported During 880415 Telcon W/Nrc Regional Ofc.Evaluating Condition W/ Mfg.Next Rept Will Be Submitted by 880715 ML20154E4641988-05-13013 May 1988 Part 21 & Deficiency Rept Re Belleville Washer Failures in Cutler-Hammer Motor Control Ctrs.Initially Reported During 880415 Telcon.Exam of Failed Washers Showed Failure Due to Intergranular Decohesion.Detailed Rept Expected by 880715 ML20151A7511988-04-0404 April 1988 Final Significant Deficiency Rept 215 Re App R Safe Shutdown Capability for Fire Area 75.Diesel Generator Control Circuits Redesigned & re-reviewed Electrical Schematics & Application of Class 1E Isolation Relay ML20149N0931988-02-23023 February 1988 Final Deficiency Rept 221-2 Re Discrepancy Between Internal Control Wiring on Three Westinghouse Dc Motor Control Ctrs & Vendor Supplied Wiring on Schematic Drawings.Initially Reported on 871103.Wiring Compartments Reworked ML20147G3671988-02-23023 February 1988 Final Significant Deficiency Rept 221-2 Re Westinghouse Dc Motor Control Ctrs.All Deficient Wiring in 20D201,20D202 & 20D203 Dc Motor Control Ctr Compartments Reworked to Approved Wiring Drawings ML20234F5781987-12-31031 December 1987 Interim Deficiency Rept 219-2 Re Wiring within Power Control Complex Found in Configurations Not Specified in Connections Diagrams 865E214TR & 807E560TR.Initially Reported on 871204.Analysis Should Be Completed by 880601 05000352/LER-1987-023, Part 21 Rept Re Reactor Protective Sys Breaker Trip. Initially Reported in Util LER 87-023.Caused by Misoperation of 27N Undervoltage Relay When Control Undervoltage Reapplied After Having Been Off1987-12-22022 December 1987 Part 21 Rept Re Reactor Protective Sys Breaker Trip. Initially Reported in Util LER 87-023.Caused by Misoperation of 27N Undervoltage Relay When Control Undervoltage Reapplied After Having Been Off ML20236V6051987-12-0202 December 1987 Interim Deficiency Rept 215 Re Fire Safe Shutdown Commitments as Documented in Section 3.2.1,Item 17 of Fire Protection Evaluation Rept.Initially Reported on 871022. Diesel Generator Control Circuits Redesigned ML20149M0971987-09-18018 September 1987 Final Deficiency Rept 213 Re High Acceleration Values for PSA-10 Snubbers.Initially Reported on 870819.All Snubber Installations That Use Size PSA-10 Snubbers Identified & Snubbers Mfg After June 1985 Will Be Installed ML20238C6301987-09-0101 September 1987 Significant Deficiency Rept 157 Re Asco Solenoid Valves on Velan air-operated Valves.Initially Reported on 840905. Completion Date for Corrective Actions Rescheduled to May 1989 Due to Const Schedule Changes.Model Number Corrected ML20238A2121987-08-24024 August 1987 Significant Deficiency Evaluation Rept 209 Re Limitorque Motor Operators W/Hydraulic Locking.Initially Reported on 870626.Limitorque Motor Operators Being Processed Through Rework Program.Item Not Reportable Per 10CFR50.55(e) ML20236P4971987-08-0505 August 1987 Advises That Corrective Actions Described in Util 870402 Deficiency Rept Complete Except for third-level Util Engineering Review & Util QA Findings.Completion of Review & Findings Anticipated by 871001 ML20236N7091987-07-31031 July 1987 Informs That Paul Munroe Actuators Have Not Been Installed to Correct Actuators Contrary to Statement in 840913 Final Significant Deficiency Rept 120.Other Mfg Being Used 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 ML20195C9771998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With ML20154H5691998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Limerick Generating Station,Units 1 & 2.With ML20151X3511998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Limerick Generating Station Units 1 & 2.With ML20237F0291998-08-27027 August 1998 Special Suppl Rept:On 960425,one Loose Part Detection Sys (Lpds) Was Identified to Be Inoperable.Initially Reported on 960531.Caused by Loose Parts Detector Module.Repairs Performed & Intermittent Ground No Longer Present ML20237D1041998-08-17017 August 1998 Books 1 & 2 of LGS Unit 1 Summary Rept for 960301-980521 Periodic ISI Rept 7 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20237B4711998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Limerick Generating Station,Units 1 & 2 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20236P9781998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Limerick Generating Station,Units 1 & 2 ML20196K1801998-06-30030 June 1998 Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with ML20249B3501998-06-11011 June 1998 Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5 ML20249A5331998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Limerick Units 1 & 2 ML20247M7071998-05-14014 May 1998 Safety Evaluation Supporting Amend 128 to License NPF-39 ML20217Q5101998-05-0404 May 1998 Safety Evaluation Supporting Amend 127 to License NPF-39 ML20247H5071998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Limerick Generating Station ML20216F3601998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Limerick Generating Station,Units 1 & 2 ML20217M0791998-03-31031 March 1998 Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216F9471998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Limerick Generating Station,Units 1 & 2 ML20216F3471998-02-28028 February 1998 Revised Monthly Operating Rept for Feb 1998 for Limerick Genrating Station,Unit 1 1999-09-30
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2830082850 PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 JOHN S. KEMPER VICE
...... . ...-PR ESI D E NT DEC 221983 Mr. Thomas E. Marley, Director United States Nuclear Regulatory Commission Office of Inspection and Enforcement, Region I 631 Park Avenue King of Prussia, PA 19406
Subject:
Significant Deficiency Report #120 Interim Report on Paul Munroe Electro-hydraulic Valve Actuators Deficiency Limerick Generating Station, Units 1 & 2 NRC Construction Permit Nos. CPPR 106 & 107 Ref erence : Telecon record J.P. Evans /R.B. Atkinson PECO-QA to Walter Baunack, USNRC dated 11/22/83 File: QUAL 2-10-2 (SDR #120) ,.
Dear Mr. Murley:
This is an interim report regarding a significant deficiency on Electro-Hydraulic HVAC valve actuators supplied by Paul Munroe Hydraulics, Inc. to Limerick Generating Station.
The Limerick Generating Station has twenty eight (28) HVAC valve operators manufactured by Paul Munroe Hydraulics, Inc. Unit 1 and Common have eighteen (18) valve operators and Unit 2 has ten (10) valve operators.
Bechtel Non-Conformance Report 6866 documented the deficiencies such a.s damaged hardmre, deformed gaskets and leakage of hydraulic fluid from drain plugs at the bottom of reservoirs and from the bottom of the hydraulic manif old . Analysis of hydraulic fluid revealed that oil was heavily contaminated and did not meet the cleanliness requirement of NAS 1638, Class 6. The contaminated oil caused a varying degree of damage to most of the major components of the actuators thus requiring complete overhaul of these actuators.
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8401260303 831222 PDR ADOCK 05000352 Vf S~ PDR _
r-dF e 2830082850 m
MR. Thomas E. Murley, Director United States Nuclear Regulatory Commission Page 2 In our opinion leakage of hydraulic fluid from drain plugs at the bottom of reservoirs would have resulted in improper operation of the actuator in normal operation, since the actuator is driven by hydraulic fluid f rom the pump. Leakage of hydraulic fluid could also result in seizure of pumps. Sufficient oil may not be pumped into the accumulator because of low level of oil, thereby hydraulic energy will not be stored ,
in the accumulator. The pressure in the accumulator will also change due to leakage of hydraulic fluid. The hydraulic fluid stored in the accumulator may not be sufficient to move the actuator through 90 degree ro ta tion. The damage to critical components of actuators such as pumps, solenoid valves, and Flo-Torks due to contamination of hydraulic fluid and leakage of oil could have an adverse ef fect on the safe operation of the plant if it had gone uncorrected.
The eighteen (18) Unit 1 and Ccmmon actuators were sent back to Paul Munroe f or disassembly, inspection, scheduled elastomer replacements and repair of damaged hardware. The inspection of the disassembled components at Paul Munroe revealed various component def ects which were apparently caused by contaminated hydraulic fluid. All eighteen (18) actuators were completelf overhauled. Critical components such as pumps, solenoid control valves, accumulators, Flo-Torks , reservoirs, and filters were replaced or repaired. The reservoirs were filled with clean Fyrquel-EHC hydraulic fluid and all actuators were f unctionally tested. The oil samples were analysed and certified to meet the cleanliness requirements of NAS 1638 Class 6. Design of the drain connection at the bottom of the reservoir was upgraded to prevent oil leakage. Larger capacity filters were installed to increase the filtration capacity.
Proper operation of Unit 1 systems containing the subject valves will be verified during pre-operational activities. The Fyrquel-EHC hydraulic fluid will be sampled at the manufacturer's recommended frequencies to confirm continued cleanliness of the fluid. Unit 2 actuators will also be shipped back to the vendor for overhaul. No date has been set for this activity pending resolution of Unit 2 status.
A final report will be filed with the NRC in nine (9) months from this da te.
Sincerely, WSS/GMM/831222 Copy to: Director of Inspection and Enforcemen United States Nuclear Regulatory Commission Washington, DC 20555 S.K. Chaudhary, Resident NRC Inspector (Limerick)