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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
[Table view] |
Text
. _ . - - - _ _ . . . . - - . . _ - - . ~ . - - . _
4 Public Service 2
Electnc and Gas Company E. C. Simpson Public Service Electric and Gas Cornpany P.O. Box 236, Hancocks Bridge, NJ 08038 609 4 39-1700 h e,.. . - ry-"
l DEC 2 81995 LR-N95244 United States Nuclear Regulatory Commission i' Document Control Desk Washington, DC 20555 Gentlemen:
a 10CFR21 INTERIN REPORT -
SCRAN DISCEARGE VOLUNE DRAIN VALVE FAILURE NOPE CREEK GENERATING STATION
- FACILITY OPERATING' LICENSE NO. NPF-57
. DOCKET NO. 50-354
)
, Pursuant to the notification requirements of 10CFR21.21(a) (2), j Public Service Electric & Gas Company (PSE&G) hereby provides the ,
attached interim report regarding failure of Scram Discharge j Volume (SDV) drain valve 1BFHV-F011. This failure is considered !
potentially reportable in accordance with 10CFR21. However, j further evaluation is required to determine the root cause of I this failure, and if this failure mechanism constitutes a Deviation as definen in 10CFR21.3(e). Therefore, a determination whether the condition is reportable under 10CFR21 can not be made i at this time. The attached provides a summary of the results of the investigation completed to date, and actions planned to evaluate this deficiency and determine reportability in 1 accordance with 10CFR21. The final determination of
- reportability will be completed prior to restart of Hope Creek ;
from the current refueling outage presently scheduled for j February 6, 1996.
- i
! Please contact us should you have any questions regarding this submittal.
Sincerely, ,
-f 06/?] '
l 050017 Attachment i
9601050092 951228 ~ ~' '"
PDR ADOCK 05000354 S pon Prtrded on l l Recycled Paper 1
DEC 2 8 EE6 Document Control Desk 2 i LR-N95244 l l
C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North i 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. R. Summers (X24)
Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 J
_ _ _ _ . . _ . _ _ _ _ . _ . . _ _ _ __ _ _ _ . . _ . . . .~ _ _ . . . _ - ___
l V l
. . I LR-N95244 ATTACHMENT l
10CFR21 INTERIN REPORT -
SCRAN DISr'N1985 VOLUNE DRAIN VALVE FAILURE EOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 l DOCKET NO. 50-354 '
I. BACKGROUND 1
I Scram Discharge Volume (SDV) Drain Valves (1BFHV-F011 & F181) are redundant air operated valves installed in series that are normally open to keep the SDV drained, and are automatically closed following a reactor scram. The SDV drain valves are 2 inch 2500 lb. globe valves that were manufactured by Hammel Dahl !
which is now owned and serviced by Neles Jamesbury. These valves are designed such that in the event of a single failure, isolation of the SDV drain line is ensured to prevent the loss of reactor coolant inventory. Should failure of both SDV drain valves occur, this could result in a flow path from the reactor-pressure vessel through the SDV.
While performing the monthly surveillance test in accordance with Technical Specification 4.1.3.1.1 for SDV drain valve 1BFHV-F011 on September 9, 1995, the monitoring instrumentation did not actuate to indicate that the valve was fully closed. Further
! investigation determined the measured valve travel was 7/8 inch instead of the expected 1-1/8 inch travel. When the valve was l stroked a second time, it was observed that the spring tension on
- the actuator was completely relaxed when the valve was in the
- closed position. This prevented the valve from going to the i fully closed position. It was concluded at that time that the
- cause of the incomplete closure was due to the spring adjuster on l the valve stem backing off the spring, possibly due to vibration.
- The spring adjuster was tightened to provide positive valve i closure. The valve was then retested and declared operable within the required Technical Specification allowed outage time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
II. EVALUATION An evaluation of possible causes of the failure has been performed. The evaluation included (1) a review of plant documentation including incident reports / problem reports, work orders and drawings, (2) a review of vendor documentation including drawings and engineering data, and (3) discussions with ,
site personnel and valve engineering personnel.
It was initially identified that the cause of the failure of SDV l drain valve 1BFHV-F011 was the result of the spring adjuster 4 Page 1 of 5 I
4 n
f
--n w ~w-~ -w n-- -+
LR-N95244 ATTACHMENT backing off the spring. Further evaluation identified three (3) possible failure mechanisms including changes in the spring
- adjuster setting during normal operation which could result in loss of spring compression. Loss of spring compression could i result in the valve sticking open due to hydraulic forces present j
when the valve is required to close "ollowing a reactor scram.
The following is a discussion of the three (3) possible failure j mechanisms:
I spring Mis-adjustment -
1 l Following actuator disassembly (such as for diaphragm j replacement), reset of the spring adjuster is required.
j Following completion of some maintenance activities such as i -replacement of valve packing, resetting of the spring adjuster may be performed. If the adjustment is not performed in accordance with the vendor's instruction, the adjustment may
- result in the spring being nearly or completely unloaded with the valve in the closed position.
change in spring Adjuster setting Due to Normal Operation -
i The existing valve design does not include a locking device to maintain the spring adjuster in its set position. Vibration or normal cycling of the valve may result in the spring adjuster i backing out from its original set position. This failure
- mechanism could also be a result of spring mis-adjustment as i discussed above if the spring is nearly or completely unloaded i with the valve in the closed position. The design relies o4 .
l frictional loads between the threads in the actuator stem and l spring adjuster to prevent movement of the spring adjuster.
spring Relaxation -
- The stresses of the actuator spring are greatest in the normally open position. If the stresses at this position exceed the yield
! point due to mis-adjustment, a defective spring or a design
- deficiency, compression set may occur which would reduce the 4 compression in the closed position. If the compression set changes over time, the spring compression may reduce sufficiently to keep the valve from fully closing.
III. DISCUSSION i
Evaluation has determined that the three possible failure i
mechanisms discussed above could affect the SDV drain valves
- IBFHV-F011 and 1BFHV-F181, and SDV vent valves 1BFHV-F010 and 1BFHV-F180.
- Page 2 of 5
~
I
! - LR-N95244 l- ATTACHMENT A review of operating experience for the SDV drain valves was i; performed to determine if evidence exists to directly support the i failure mechanisms proposed above. A review of monthly and quarterly surveillance test results was performed. In general, i the SDV drain valves have tested satisfactorily, and no failures i were identified related to incomplete valve closure. The five
- second time delay between the closure of the inboard and outboard drain valves sometimes requires readjustment. Readjustment typically consists of slightly changing the regulated air pressure so that the time needed to bleed down the air is changed.
4 Some maintenance has been performed on valve 1BFHV-F011 that
'would require reset of the spring adjuster from initial receipt
- - from the manufacturer. In 1989, the diaphragm was replaced which
. required spring removal. In 1991, the actuator was rebuilt which required spring readjustment. As of the date of the failure, no i work activities on the valve were identified since 1991 that l would have reset the spring adjuster. In addition, no preventive i maintenance requirements were identified by the vendor for the ,
- valves to ensure proper spring adjustment is maintained.
- l A failure of 2500-lb Hammel Dahl SDV vent and drain valves was !
] reported to the NRC (see NRC Information Notice 86-82, Revision
! 1). These failures were attributed to the manual handwheel not being positioned in the neutral position which resulted in the i deformation and disengagement of the coupling between the
. actuator stem and valve stem when the valve was operated. This
! failure does not appear to be a possible cause for loss of spring compression.
! This model actuator and other similar models are not provided l with locking devices. The design relies on frictional loads j between the threads in the actuator stem and spring adjuster to j prevent movement of the spring adjuster. The valve is normally 1 open which is when the spring is under its maximum compression. '
}
The frictional loads resisting loosening are also maintained
- during this period. Neles-Jamesbury does not use a locking device on any spring adjuster for the actuator model in question, or the new actuator model that has replaced it.
} Neles-Jamesbury has indicated that valve / actuator combinations of ;
i this configuration have never been reported to have lost spring compression either-by the adjuster becoming loose or spring ,
i relaxation. Seismic qualification testing on a similar 2 inch j valve with a frame yoke actuator has been performed. The results 3
showed that the valve was operating acceptably after the j vibration test. Although not specifically identified for 1
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LR-N95244 ATTACHMENT inspection, no indication was given that the stem adjuster loosened during the test.
Industry operating experience indicates that helical springs in
- compression over an extended period of time can develop some relaxation or compression set (See NRC Information Notice 89-43).
< Based on the vendor information for this model valve, a compression set of 0.3 inches (with a nominal free spring length of 9 inches) is sufficient to unload the spring in the closed position.
) IV.
SUMMARY
AMD CORRECTIVE ACTIOMS l
- Both SDV drain valves 1BFHV-F011 and 1BFHV-F181 and the SDV vent
- valves 1BFHV-F010 and 1BFHV-F180 are susceptible to each of the
- three possible failure mechanisms. The identified failure could a have resulted from a deficiency in the design of the valve and j actuator including the spring, or due to lack of proper valve j maintenance requirements. However, insufficient information is
- presently available to determine the specific root cause of the i
- failure, and if this failure mechanism constitutes a Deviation as j defined in 10CFR21.3(e). Therefore, a determination whether the
- condition is reportable under 10CFR21 can not be made at this j time.
j Further investigation is ongoing to identify the root cause and 4
necessary corrective actions, and determine reportability. This investigation will consist of the following:
(1) measuring valve stroke versus air pressure for each of the four affected SDV drain and vent valves both with and without stem packing loads applied, (2) removing the spring from valve 1BFHV-F011, and measuring the physical dimensions, spring rate and selected material properties, and (3) confirming that the spring and spring adjuster design are adequate to maintain spring compression for valve closure.
Items 1 through 3 above will be completed prior to restart of Hope Creek from the current refueling outage presently scheduled
. for February 6, 1996. The results of Items 1 through 3 will be used to complete the root cause determination, and the evaluation to determine if this condition is reportable under 10CFR21. The final determination of reportability will be completed prior to 4 restart.
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LR-N95244 ATTACHMENT '
To prevent the spring adjuster from backing off the spring resulting in loss of spring compression, PSE&G will also install '
a locking device for the spring adjuster on the SDV vent and drain valves. This modification will also be completed prior to restart.
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