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| Pubbe Service Decnic and Gas Company , | | Pubbe Service Decnic and Gas Company , |
| Stunley LaBruna Pubhc Service Doctnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 vu e. o . w a cs e x. | | Stunley LaBruna Pubhc Service Doctnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 vu e. o . w a cs e x. |
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| report of a misapplication of Magnetrol Level Switches supplied ! | | report of a misapplication of Magnetrol Level Switches supplied ! |
| by General Electric Company with the High Pressure Coolant I Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) turbine assemblies for the Hope Creek Generating Station (HCGS). | | by General Electric Company with the High Pressure Coolant I Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) turbine assemblies for the Hope Creek Generating Station (HCGS). |
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| As described'in Attachment 1, and in our telephone notification (S. ' La Bruna to H. Thompson) on this date, PSE&G determined, on k7 , | | As described'in Attachment 1, and in our telephone notification (S. ' La Bruna to H. Thompson) on this date, PSE&G determined, on k7 , |
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| November 16, 1989, that a design misapplication exists for the subject Magnetrol level switch assemblies. i i | | November 16, 1989, that a design misapplication exists for the subject Magnetrol level switch assemblies. i i |
| Please contact us if you have any questions with regard to this l transmittal. ! | | Please contact us if you have any questions with regard to this l transmittal. ! |
| t Sincerely, , | | t Sincerely, , |
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| | Document Control Desk 2 November 20, 1989 NLR-N89232 C Mr. C. Y. Shiraki Licensing Project Manager l Mr. D. K. Allsopp Resident Inspector Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering l -. |
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| Document Control Desk 2 November 20, 1989 NLR-N89232 | |
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| C Mr. C. Y. Shiraki Licensing Project Manager l Mr. D. K. Allsopp Resident Inspector Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering l -. | |
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| SUBJECT! 10CFR PART 21 - MISAPPLICATION OF MAGNETROL LEVEL SWITCH - NODEL 5.0-751-XXXX (PART $57-3003-006 WITEOUT FIN SECTION) SUPPLIED BY GE WITH MPCI AND RCIC TURBINE ASSEMBLIES | | SUBJECT! 10CFR PART 21 - MISAPPLICATION OF MAGNETROL LEVEL SWITCH - NODEL 5.0-751-XXXX (PART $57-3003-006 WITEOUT FIN SECTION) SUPPLIED BY GE WITH MPCI AND RCIC TURBINE ASSEMBLIES |
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| The qualified life of the level switgh was originally determined by_GE to be 6.5 ygars based on a 235 F temperatureg at the microswitch, a 72 F ambient temperature, and a 560 F process fluid temperature. Subsequently,gGE provided a revised qualified life of 1.65 years based on a 260 F temperature at the | | The qualified life of the level switgh was originally determined by_GE to be 6.5 ygars based on a 235 F temperatureg at the microswitch, a 72 F ambient temperature, and a 560 F process fluid temperature. Subsequently,gGE provided a revised qualified life of 1.65 years based on a 260 F temperature at the |
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| | * ATTACHMENT 1 - Cont'd microswitch, a 108 F ambient temperature, and a 575 F process fluid temperature. This qualified gife was adjusted by PSE&G to 2.1 years using temperatures of 255 F at the microswitch, calculatedbyusgngtheGEformulaandHCGSparametersof92F ambient, and 581 F for the process fluid. |
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| ATTACHMENT 1 - Cont'd microswitch, a 108 F ambient temperature, and a 575 F process fluid temperature. This qualified gife was adjusted by PSE&G to 2.1 years using temperatures of 255 F at the microswitch, calculatedbyusgngtheGEformulaandHCGSparametersof92F ambient, and 581 F for the process fluid. | |
| The above qualified life could not be achieved at Hope Creek Generating Station. | | The above qualified life could not be achieved at Hope Creek Generating Station. |
| Based upon the recorded actual temperature at the microswitch and | | Based upon the recorded actual temperature at the microswitch and the experience of the frequent failure of the Magnetrol Level Switches, as supplied by GE, we have concluded that there is a misapplication of these switches at HCGS and that 10CFR, Part 21 applies. ; |
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| the experience of the frequent failure of the Magnetrol Level Switches, as supplied by GE, we have concluded that there is a misapplication of these switches at HCGS and that 10CFR, Part 21 applies. ; | |
| A potential safety hazard is created wherein, if one of the level switches fails at the same time that the normal drain trap on its , | | A potential safety hazard is created wherein, if one of the level switches fails at the same time that the normal drain trap on its , |
| associated steam supply line also fails, condensation could build up on the inlet side of a HPCI or RCIC turbine. Then, upon a , | | associated steam supply line also fails, condensation could build up on the inlet side of a HPCI or RCIC turbine. Then, upon a , |
| demand to start the affected pieca of equipment, damage to the r | | demand to start the affected pieca of equipment, damage to the r turbine could result in its inability to perform its intended function. |
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| turbine could result in its inability to perform its intended function. | |
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| PSE&G has taken the following corrective action: 1) declare the subject level switches inoperable, 2) electrically disconnect the switches, and 3) open the steam trap bypass valves and defeat t their controls in that position on the HPCI and RCIC turbine steam supply lines, thereby ensuring no collection of . | | PSE&G has taken the following corrective action: 1) declare the subject level switches inoperable, 2) electrically disconnect the switches, and 3) open the steam trap bypass valves and defeat t their controls in that position on the HPCI and RCIC turbine steam supply lines, thereby ensuring no collection of . |
| condensation that could degrade the operability of the turbines. . | | condensation that could degrade the operability of the turbines. . |
| t The longer term corrective action is to have the vendor, Magnetrol, modify our spare level switch assemblies to include an extended, cooling-finned section between the condensate pot portion and the microswitch and of the assemblies. This modified switch assembly design is qualified to IEEE 323-1974 and IEEE 344-1975 and will result in temperatures at the microswitch which will return to within the GE qualified life basis. | | t The longer term corrective action is to have the vendor, Magnetrol, modify our spare level switch assemblies to include an extended, cooling-finned section between the condensate pot portion and the microswitch and of the assemblies. This modified switch assembly design is qualified to IEEE 323-1974 and IEEE 344-1975 and will result in temperatures at the microswitch which will return to within the GE qualified life basis. |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG 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 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 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 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 ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils 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 ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20096A4021995-12-28028 December 1995 Interim Part 21 Rept Failure of Scram Discharge Vol Drain Valve 1BFHV-F011.Possible Causes of Failure,Includes Spring mis-adjustment,change in Spring Adjuster Setting & Spring Relaxation.Further Investigation Ongoing ML20082S7401995-04-26026 April 1995 Part 21 Rept Re Hinge Arms Associated W/Sixteen Swing Check Valves Mfg by Anchor-Darling Valve Co ML20081L7701995-03-29029 March 1995 Initial Part 21 Rept Re Anchor-Darling Check Valve Hinge Arms.Cs Pump B Discharge Check Valve Failed to Close in Nov 1994 Because Butt Stop on Hinge Arm Not of Sufficient Length.New Butt Stop Hinge Arm,Hinge Pin & Disc Installed ML20063M1701994-03-0202 March 1994 Part 21 Rept Clarifying & Supplementing Info Provided by Licensee Re Deficiency in Qualified Life Calculation for Microswitches Mfg by Comsip,Inc. Subj PTW-5300 Dc Indicators Supplied by Comsip,Inc,Mfg by Microswitch Corp ML20046C6591993-08-0505 August 1993 Part 21 Rept:On 930429,deficiency Identified Re Heat Damage to Comsip Series PTW-5300 Dc Powered Microswitches.Initially Reported on 930709.Safety-related Dc Microswitches Will Be Replaced Prior to 931230 ML20128H9931993-02-0909 February 1993 Interim Deficiency Rept Re Defect in Replacement EDG Fuel Oil Pumps Supplied by Colt Industries (Fairbanks Morse Engine Div).Initially Reported on 930111.Plugs & O-rings Repositioned.Vendor Requested to Perform Evaluation ML18096B2421993-02-0101 February 1993 Part 21 Rept Re Possible Matl Defect in Stainless Steel Swagelock Tube Fittings.Initially Reported on 921218.List of Part Numbers,Heat Codes & Addl Affected Customers Encl ML20127K8811993-01-0606 January 1993 Part 21 Rept Re Engine Driven Fuel Oil Pump Being Returned for Proper Configuration Due to Portion of O Ring Missing from Plug ML20116L4311992-10-20020 October 1992 Followup to Part 21 Rept from Consolidating Power Supply, Inc Re Purchase & Procurement of 24-inch Flange at Facility Which Failed to Meet ASME Code Class III Requirements.Flange Purchased by Conex Pipe Sys,Inc.Investigation Underway ML20101L0791992-06-29029 June 1992 Final Part 21 Rept Re Defect in Assembly Process for Gh Bettis Containment Atmosphere Control Sys Valve Replacement Actuators.Initially Reported on 920529.Air Filter Installed in Compressor Main Air Line to Prevent Contamination ML20102B2071992-06-24024 June 1992 Part 21 Rept Re Cracking of Stellite 21 Hardfacing on Guide Nose of Poppets Supplied as Part of MSIV Leakage Improvement Mod.Initially Reported by Clei on 920522. Recommends That Liquid Penetrant Exam Be Performed ML20097D9111992-06-0303 June 1992 Part 21 Rept Re Design Defect in Degraded Grid Trip & Bus Transfer Scheme for Class IE Vital Busses Supplied by Bechtel Power Corp.Initially Reported on 920508.Design Change Package 4EC-3341 Issued & Implemented ML20097H1581992-05-29029 May 1992 Initial Part 21 Rept Re Failure of Gh Bettis Actuators Used at Plant.Gh Bettis Has Ordered Replacement SOVs & Pilot Valves for Installation at Butterfly Valve Mfg,C&S Valve ML20102B1041992-05-0808 May 1992 Part 21 Rept Re Defect Discovered in Degraded Grid Trip/Bus Transfer Scheme for Class IE Vital Bus Equipment.Time Delay of .7 Incorporated in Loading Scheme to Allow Loads to Drop Off of auto-swapped Class IE Buses ML20077N3491991-08-0909 August 1991 Part 21 Rept Re Potential for Malfunction of Filtration Recirculator Ventilation Sys Heater Control Panels at Plant Due to Excessive Heat Rise.Heater Control Panel Doors Removed ML20077J9641991-07-30030 July 1991 Interim Deficiency Rept Re Potential Deviation of Design Safety Function of Filtration Recirculator Ventilation Sys Heaters Controls Panels.Further Investigation Required to Determine If Defect Requires Notification,Per 10CFR21 ML19332C5831989-11-20020 November 1989 Part 21 Rept Re Misapplication of Magnetrol Level Switches Supplied by GE W/Hpci & RCIC Turbine Assemblies.Switches Declared Inoperable & Electrically Disconnected.Magnetrol Will Modify Spare Level Switch Assemblies ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20210S3351987-02-0404 February 1987 Part 21 Rept Re Cracking in O-ring on Latch Mechanism on Contactors in Nuclear Exciters.Initially Reported on 861216. Sprecher & Schuh Changed O-ring Matl to Viton E60C. Contactors Will Be Returned to Vendor & Rebuilt ML20214E9231987-01-28028 January 1987 Part 21 Rept Re Incorrect Valve Stem Matl on Dragon Valves. Evaluation Underway.Owners or Architects/Engineers & NRC Will Be Notified of Results of Evaluation & Recommendations ML20215B9681986-09-26026 September 1986 Part 21 & Deficiency Rept Re Synchro-Start Type Essb Speed Switches.Initially Reported on 860822.Speed Switches Currently in Svc or Designated for Svc Will Be Tested for Relay Contact Closure & Relay Contact Condition ML20212N1371986-08-25025 August 1986 Part 21 Rept Re Potentially Defective Operation of Synchro-Start Products,Inc Synchronizing Speed Switches Used in Auxiliary Generating Equipment.Initally Reported on 860820.Next Rept Will Be Submitted by 860926 ML20211C6181986-06-0909 June 1986 Part 21 Rept Re Unknown Qualification of Yokogawa Type AB 40 Voltmeters & Ammeters Due to Unreported Design & Configuration Changes.Three Nuclear Plants Receiving 23 Items as Class 1E Spare Parts Notified.List of Users Encl ML20141E4361986-04-0101 April 1986 Final Significant Const Deficiency Rept Re Failure of Electrical Amplifier Assembly in Tobar Transmitters to Function During Irradiation Testing.Initially Reported on 860303.Seven Transmitters Will Be Replaced ML20141E4411986-04-0101 April 1986 Final Significant Const Deficiency Rept Re Anchor-Darling Testable Check Valves Not Opening/Closing Under Normal Operating Conditions.Initially Reported on 860305.Valves Modified to Improve Mechanism for Opening/Closing Disc ML20140J4261986-03-31031 March 1986 Part 21 Rept Re Nuclear Valves Shipped to Pse&G.Internal Parts Lapped Which Could Reduce or Eliminate Nickel Plating Resulting in Seat Leakage & Shifting Problems ML20210E0031986-03-17017 March 1986 Part 21 Rept Re Failure of Amplifiers at Hope Creek Plant During Gamma Radiation Testing.Initially Reported on 860314. Util Supplied W/List of Model 32 Transmitters Which Meet Criteria ML20199E9161986-03-0707 March 1986 Final Significant Const Deficiency Rept Re Overspeed Trip on Emergency Diesel Generator Mfg by Colt Industries.Initially Reported on 860213.All Colt-Pielstick PC-2 Engines Will Be Modified by 860415 ML20141N6501986-03-0505 March 1986 Final Deficiency Rept Re Environ Qualification of Tobar Pressure Transmitter Terminations.Initially Reported on 860205.Pressure Transmitters Reworked & Discrepancy & Startup Deviation Repts Issued ML20154H2191986-03-0303 March 1986 Part 21 & Deficiency Rept Re Tobar Model 32-2 Transmitters W/Steel,Not Polyester or Aluminum Amplifier Housings. Initially Reported on 860227.Preliminary Investigation Confirms Adequacy of Transmitters ML20141N7011986-02-26026 February 1986 Suppl to Final Significant Const Deficiency Rept Re Anchor/Darling Swing Check Valves.Eight Valves W/O Lock Welds Reworked ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20137U8461986-02-0303 February 1986 Significant Const Deficiency Rept Re Inadequate Power to Tobar Pressure Transmitters.Initially Reported on 860115. Design Change Package (DCP-7153) Issued to Modify Power Supply Circuits ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20137Z1611985-11-21021 November 1985 Final Part 21 & Significant Deficiency Rept Re Ruskin Mfg Co Spring Closure Fire Dampers.Initially Reported on 841224. Dampers Reworked & in-place Testing Program to Identify Limiting Airflow Conditions Implemented ML20137S1031985-11-0606 November 1985 Final Part 21 & Significant Const Deficiency Rept Re Heat Buildup Inside Generator Control Cabinets.Initially Reported on 850403.Design Change Packages 570 & 7079 Implemented. Current Transformers Replaced ML20138K2731985-10-11011 October 1985 Final Part 21 & Const Deficiency Rept Re Missing Lock Welds on Anchor/Darling Swing Check Valves.Initially Reported on 850911.Set Screws Staked During Insp & Disc Nut Pins Peened as Alternative to Lock Welding ML20133N8211985-10-10010 October 1985 Final Const Deficiency Rept Re Misoperation of Bailey Controls Co 862 Sys Logic Module Logic Memories During Environ Qualification Testing.Initially Reported on 850909. Gap in Circuit Board Pads Increased & Area Cleaned 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 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 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced1999-04-12012 April 1999 Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With 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 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 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 ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 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 LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1 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 ML18106A5851998-03-0303 March 1998 Emergency Response Graded Exercise,S98-03. Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08
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Pubbe Service Decnic and Gas Company ,
Stunley LaBruna Pubhc Service Doctnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 vu e. o . w a cs e x.
November 20, 1989 NLR N89232 U.S. Nucluar Regulatory Commission Document Control Desk Nashington, DC 20555 I Gentlement i 10CFR21 NOTIFICATION - MISAPPLICATION OF NAGNETROL LEVEL SWITCH i HPCI AND RCIC TURBINE STEAN SUPPLY DRAIN VALVES l HOPE CREEK GENERATING STATION l FACILITY OPERATING LICENSE NO. NPF-57 j DOCKET NO. 50-354 j Pursuant to the notification requirements of 10CFR Part 21, Public Service Electric and Gas Company (PSE&G) hereby provides a !
report of a misapplication of Magnetrol Level Switches supplied !
by General Electric Company with the High Pressure Coolant I Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) turbine assemblies for the Hope Creek Generating Station (HCGS).
As described'in Attachment 1, and in our telephone notification (S. ' La Bruna to H. Thompson) on this date, PSE&G determined, on k7 ,
November 16, 1989, that a design misapplication exists for the subject Magnetrol level switch assemblies. i i
Please contact us if you have any questions with regard to this l transmittal. !
t Sincerely, ,
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Document Control Desk 2 November 20, 1989 NLR-N89232 C Mr. C. Y. Shiraki Licensing Project Manager l Mr. D. K. Allsopp Resident Inspector Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering l -.
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SUBJECT! 10CFR PART 21 - MISAPPLICATION OF MAGNETROL LEVEL SWITCH - NODEL 5.0-751-XXXX (PART $57-3003-006 WITEOUT FIN SECTION) SUPPLIED BY GE WITH MPCI AND RCIC TURBINE ASSEMBLIES
REFERENCE:
GE Environmental Qualification Report No. NEDC-30433, Magnetrol Level Switches, dated April, 1985 On November 16, 1989, PSE&G determined the misapplication of the Magnetrol Level Switches supplied by General Electric Company with the HPCI and RCIC turbine assemblies for Hope Creek Generating Station. The subject switches, upon indication of condensation buildup in the steam supply line to either the HPCI or RCIC turbine, actuate automatic bypass of the normal low point drain trap on the affected line.
The PSE&G Equipment Identification for the subject level switches at HCGS are:
1FCLSH-N010-E51 Magnttrol Level Switch for the RCIC Turbine 1FCLSH-N014-E41 Magnetrol Level Switch for the HPCI Turbine PSE&G has been experiencing failure of the subject switches at much shorter intervals than those specified by GE in the above-referenced qualification Report.
PSE&G has been replacing these swi:ches as necessary while investigating the root cause for the failures and evaluating potential alternative switches. 7he failures of the microswitch within the level switch housing is apparently due to excessive heat. As part of the investigation, PSE&G measured the temperature inside the level switch hgusing at the microswitch, recording temperatures as high as 335 F.
A review of the GE qualification report has determiged that, originally, a temperature at the microswitch of 235 F vas used by GE in determining the design application and the qualified life of the level switch for HCGS application. However, GE also had provided, in the report, revised calculations based on varying process fluid temperatgre wherein the temperature at the micro switch could reach 264 F.
The qualified life of the level switgh was originally determined by_GE to be 6.5 ygars based on a 235 F temperatureg at the microswitch, a 72 F ambient temperature, and a 560 F process fluid temperature. Subsequently,gGE provided a revised qualified life of 1.65 years based on a 260 F temperature at the
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- ATTACHMENT 1 - Cont'd microswitch, a 108 F ambient temperature, and a 575 F process fluid temperature. This qualified gife was adjusted by PSE&G to 2.1 years using temperatures of 255 F at the microswitch, calculatedbyusgngtheGEformulaandHCGSparametersof92F ambient, and 581 F for the process fluid.
The above qualified life could not be achieved at Hope Creek Generating Station.
Based upon the recorded actual temperature at the microswitch and the experience of the frequent failure of the Magnetrol Level Switches, as supplied by GE, we have concluded that there is a misapplication of these switches at HCGS and that 10CFR, Part 21 applies. ;
A potential safety hazard is created wherein, if one of the level switches fails at the same time that the normal drain trap on its ,
associated steam supply line also fails, condensation could build up on the inlet side of a HPCI or RCIC turbine. Then, upon a ,
demand to start the affected pieca of equipment, damage to the r turbine could result in its inability to perform its intended function.
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PSE&G has taken the following corrective action: 1) declare the subject level switches inoperable, 2) electrically disconnect the switches, and 3) open the steam trap bypass valves and defeat t their controls in that position on the HPCI and RCIC turbine steam supply lines, thereby ensuring no collection of .
condensation that could degrade the operability of the turbines. .
t The longer term corrective action is to have the vendor, Magnetrol, modify our spare level switch assemblies to include an extended, cooling-finned section between the condensate pot portion and the microswitch and of the assemblies. This modified switch assembly design is qualified to IEEE 323-1974 and IEEE 344-1975 and will result in temperatures at the microswitch which will return to within the GE qualified life basis.
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