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| {{#Wiki_filter:JUN-01-1999 10:42 N L I *-817 590 0484 P.01/01 June 1, 1999 NCR-73-02 | | {{#Wiki_filter:JUN-01-1999 10:42 NL I NLI NUCLEAR LOGISTICS INC |
| .. Document Control Desk
| | *- 817 590 0484 P.01/01 June 1, 1999 NCR-73-02 Document Control Desk United States Regulatory Commission Washington, DC 20555 FAX (301).816-5151 |
| * United States Regulatory Commission Washington, DC 20555 FAX (301).816-5151 NLI NUCLEAR LOGISTICS INC
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| ==Subject:== | | ==Subject:== |
| Interim Report of a Deviation Nuclear Logistics presents the following infonnation in accordance with 10CF.R21, §21.2l(a)(2) . concerning a deviation, which has identified. | | Interim Report of a Deviation Nuclear Logistics presents the following infonnation in accordance with 10CF.R21, §21.2l(a)(2) |
| i) Information submitted by: Mr. Aron Seiken Preside.nt Nuclear Logistics Incorporated 7450 Whitehall Street Fort Worth, TX 76118 Telephone: | | . concerning a deviation, which has b~en identified. |
| (817) 284-0077 Facsimile: | | i) Information submitted by: Mr. Aron Seiken Preside.nt Nuclear Logistics Incorporated 7450 Whitehall Street Fort Worth, TX 76118 Telephone: (817) 284-0077 Facsimile: (817) 590-0484 ii) The item with the deviation is a NLI DC Power Supply, PIN NLI-LGS-G-24-0V-R-8018. |
| (817) 590-0484 ii) The item with the deviation is a NLI DC Power Supply, PIN NLI-LGS-G-24-0V-R-8018. | | iii) NL! has supplied these power supplies as Class lE components. |
| iii) NL! has supplied these power supplies as Class lE components. | | iv) The deviation, which has been identified, is premature over voltage protection actuation in a circuit specific application. The premature over voltage protection actuat~on occurred during diesel generator start up. Specifically, the premature over voltage protection actuation* occurs during diesel generator loading. |
| iv) The deviation, which has been identified, is premature over voltage protection actuation in a circuit specific application. | | v) This issue was determined to be a deviation on April 19, 1999. |
| The premature over voltage protection occurred during diesel generator start up. Specifically, the premature over voltage protection actuation* | | vi) These components have been supplied as safety*related components to the following facility: |
| occurs during diesel generator loading. v) This issue was determined to be a deviation on April 19, 1999. vi) These components have been supplied as safety*related components to the following facility: | | : 1) Public Service Electric and Gas Company vii) To date, NLI has been unable to duplicate the premature over voltage protection actuation during laboratory testing. Data collection and additional testing is being performed to resol,.*e the 1/ |
| : 1) Public Service Electric and Gas Company vii) To date, NLI has been unable to duplicate the premature over voltage protection actuation during laboratory testing. Data collection and additional testing is being performed to resol,.*e the deviation. | | deviation. If the premature over voltage protection actuation is determined to be the result of the power supply design, other NLI-L series power supplies will be tested to determine their |
| If the premature over voltage protection actuation is determined to be the result of the power supply design, other NLI-L series power supplies will be tested to determine their to similar conditions. | | ;~iii!)' to similar conditions. Testing and evaluation activities will be completed on July viii) The results of testing to date has been discussed with the .cognizant personnel at the facility identified in section vi oftbis interim report. |
| Testing and evaluation activities will be completed on July 1 / viii) The results of testing to date has been discussed with the .cognizant personnel at the facility identified in section vi oftbis interim report. Should you require clarification, or additional information, please contact Mr. Archie C. Bell or me. Very Yours:_ j ftR Aron Seiken President 7450 Whiteh-.11 | | Should you require clarification, or additional information, please contact Mr. Archie C. Bell or me. |
| *Fort Worth, TX 76118 Telephone (817) 284*0077 | | Very T~.- Yours:_ j n_~,E~cf)~ |
| * Fax (817) 590-0484 ------------\ TOTAL P.01 | | ftR Aron Seiken President 7450 Whiteh-.11 *Fort Worth, TX 76118 Telephone (817) 284*0077 |
| ''-' -#
| | * Fax (817) 590-0484 |
| * 0'610111999 U.S. Nu.r Regulatory Commission Operations Cente.nt Report ,, I .*General Information or Other (PAR) Event# 35782 -Rep Org: NUCLEAR LOGISTICS INC Notification Date I Time: 06/01/1999 11 :07 (EDT) Supplier:
| | -- -- --- -- ---\ |
| NUCLEAR LOGISTICS INC Event Date I Time: 04/19/1999 (CDT) -Last Modification: | | TOTAL P.01 |
| 06/01/1999 Region: 4 Docket#: City: FORT WORTH Agreement State: Yes County: License#: | | |
| State: TX NRC Notified by: SEIKEN (FAX) Notifications: | | -- ~ |
| VERN HODGE(FAX) | | 0'610111999 |
| NRR HQ Ops Officer: CHAUNCEY GOULD RICHARD CONTE R1 Emergency Class: NON EMERGENCY 10 CFR Section: 21.21 UNSPECIFIED PARAGRAPH 1 J PART 21 DEVIATION IN A NUCLEAR LOGISTICS INC (NLI) DC POWER SUPPLY. A DEVIATION HAS BEEN IDENTIFIED IN A NLI DC POWER SUPPLY, P/N NLl-LGS-G-24-0V-R-8018 WHICH HAVE BEEN SUPPLIED AS A CLASS 1E COMPONENT, THAT ALLOWS A PREMATURE OVER VOLTAGE PROTEGllON ACTUATION TO OCCUR IN A CIRCUIT SPECIFIC APPLICATION. | | * U.S. Nu.r Regulatory Commission Operations Cente.nt Report I |
| THIS CONDITION OCCURRED"b>URING DIESEL GENERATOR STARTUP, SPECIFICALLY DURING DIESEL GENERATOR LOADING. THIS*ISSUE W..AS DETERMINED TO BE A DEVIATION ON 4/19/99, HOWEVER, TO DATE NLI HAS NOT BEEN ABLE TO DUPLICATE THIS CONDITION DURING LABORATORY TESTING. DATA COLLECTION AND-ADDITIONAL TESTING IS BEING PERFORMED TO RESOLVE THE DEVIATION. | | .*General Information or Other (PAR) Event# 35782 |
| IT THE PREMATURE OVER VOLTAGE PROTECTION ACTUATION IS DETERMINED TO BE THE RESULT OF THE POWER SUPPLY DESIGN, OTHER NLl-L SERIES POWER SUPPLIES WILL BE TESTED TO DETERMINE THEIR SUSCEPTIBILITY TO SIMILAR CONDITIONS. | | - Rep Org: NUCLEAR LOGISTICS INC Notification Date I Time: 06/01/1999 11 :07 (EDT) |
| TESTING AND EVALUATION ACTIVITIES WILL BE COMPLETED ON 7/16/99. THESE COMPONENTS HAVE BEEN SUPPLIED AS SAFETY-RELATED COMPONENTS TO PUBLIC SERVICE ELECTRIC AND GAS COMPANY . --*************************************************************************************************************************************}} | | Supplier: NUCLEAR LOGISTICS INC Event Date I Time: 04/19/1999 (CDT) |
| | - Last Modification: 06/01/1999 Region: 4 Docket#: |
| | City: FORT WORTH Agreement State: Yes County: License#: |
| | State: TX NRC Notified by: SEIKEN (FAX) Notifications: VERN HODGE(FAX) NRR HQ Ops Officer: CHAUNCEY GOULD RICHARD CONTE R1 Emergency Class: NON EMERGENCY 10 CFR Section: |
| | 21.21 UNSPECIFIED PARAGRAPH 1 |
| | J PART 21 DEVIATION IN A NUCLEAR LOGISTICS INC (NLI) DC POWER SUPPLY. |
| | A DEVIATION HAS BEEN IDENTIFIED IN A NLI DC POWER SUPPLY, P/N NLl-LGS-G-24-0V-R-8018 WHICH HAVE BEEN SUPPLIED AS A CLASS 1E COMPONENT, THAT ALLOWS A PREMATURE OVER VOLTAGE PROTEGllON ACTUATION TO OCCUR IN A CIRCUIT SPECIFIC APPLICATION. THIS CONDITION OCCURRED"b>URING DIESEL GENERATOR STARTUP, SPECIFICALLY DURING DIESEL GENERATOR LOADING. THIS*ISSUE W..AS DETERMINED TO BE A DEVIATION ON 4/19/99, HOWEVER, TO DATE NLI HAS NOT BEEN ABLE TO DUPLICATE THIS CONDITION DURING LABORATORY TESTING. DATA COLLECTION AND-ADDITIONAL TESTING IS BEING PERFORMED TO RESOLVE THE DEVIATION. IT THE PREMATURE OVER VOLTAGE PROTECTION ACTUATION IS DETERMINED TO BE THE RESULT OF THE POWER SUPPLY DESIGN, OTHER NLl-L SERIES POWER SUPPLIES WILL BE TESTED TO DETERMINE THEIR SUSCEPTIBILITY TO SIMILAR CONDITIONS. TESTING AND EVALUATION ACTIVITIES WILL BE COMPLETED ON 7/16/99. THESE COMPONENTS HAVE BEEN SUPPLIED AS SAFETY-RELATED COMPONENTS TO PUBLIC SERVICE ELECTRIC AND GAS COMPANY. |
| | *************************************************************************************************************************************}} |
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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 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process 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 ML18102A3701996-09-0606 September 1996 Part 21 Rept Re Installation of NUS Model OCA 801 Signal Isolator Modules & Model Mth 801 Signal Summator Modules. Replacement Modules Including Spares for Plant,Unit 2 Have Been Inspected by Vendor & Repaired ML18102A3381996-08-21021 August 1996 Part 21 Rept Re Chipping of Latching Mechanism Props Installed in GE 4 Kv magne-blast Circuit Breakers,Type AM-4.16-350-2H.Two Affected Breakers Have Been Returned to Vendor ML18102A5591996-08-0808 August 1996 Part 21 Rept Re Defect in NUS Model OCA801 Signal Isolator Modules.Replacement Modules Installed in Reactor Control & Protection Sys 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 ML18101A8771995-08-0404 August 1995 Interim Part 21 Rept Re Potentially Reportable Deficiency in Edward Valve Model 838YT Check Valves Due to Disk Exhibiting Excessive Leakage.Disk from Original Valve Cleaned, Inspected & Installed in Replacement Valve ML18101A8611995-08-0101 August 1995 Interim Part 21 Rept Re Velan Valve Corp Check Valve Failure to Close.Insp of Internals Showed Moderate Wear in Gap Between Valve Disc & Hanger Arm.New Disc Installed & Valve Tested Satisfactorily 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 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 ML18100B2391994-07-27027 July 1994 Part 21 Rept Re Signal Summators PM-505B & 506B Found to Saturate High When Summators Lose Power & Reenergized. Summators Powered from Independent Vital Instrument Buses & Inverters.Design Changes Implemented ML18100B2271994-07-25025 July 1994 Part 21 Rept Re Cracking in Valve Stem & Plug Connection Pinning Collar Area on PORVs 1PR1 & 1PR2.Caused Attributed to Either IGSCC or Hydrogen Assisted Cracking.Porv Internals Replaced W/Internals Mfg from SS 316 Matl W/Plug Stellited ML18100B2101994-07-14014 July 1994 Deficiency Rept Re PORV Plug & Stem Material Defects. Initially Reported 940714.PORV Internals Were Replaced W/Plug Stellited ML18100B1911994-06-30030 June 1994 Initial Part 21 Rept Re Deficiency in Signal Summators PM-505B & PM-506B Supplied by Westinghouse.Design Changes Implemented & Operators Made Aware of Affects of Power Supply Transient on Summator Operability 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 ML18100A7681993-12-13013 December 1993 Interim Part 21 Rept Re Discovery That Ge/Alco EDGs High Pressure Injection Tube Studs Did Not Meet Correct Matl non- Std & Not Correct Geometry.All Nonconforming Studs Identified & Replaced 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 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl 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 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 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 ML18095A4031990-08-0202 August 1990 Part 21 Rept Re MSIV Design Deficiency at Plant.Design Spec Provided by Westinghouse Did Not Specify Requirement to Provide Seal in Capability & Util Design Process Failed to Recognize Deficiency ML18095A2321990-05-24024 May 1990 Part 21 Rept Re Discrepancies Identified in ECCS Flow Orifice K Factors Supplied by Westinghouse.Initially Reported on 900518.Util Fabricated New Orifice Plates to Original Specs ML18095A2251990-05-22022 May 1990 Part 21 Rept Re Insufficient Welds on Pedestal Support Alignment Lug & Slide Shoe for 11,12,21 & 22 Charging/Safety Injection Pumps.Initially Reported on 900516.Windows Cut in Support Pedestals to Gain Access to Affected Areas ML18094B4461990-04-27027 April 1990 Part 21 Rept Re shaft-to-pinion Key Failures in Limitorque Actuators.Initially Reported on 900424.Caused by Reduction of cross-sectional Area & Ultimate Propagation of Cracks. Util Intends to Replace Keys in Actuators W/Keys of Steel 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 ML18094A4421989-05-16016 May 1989 Part 21 Rept Re Defect in Solid State Protection Sys. During Mods in Solid State Protection Sys Cabinets,Noted That Two Wires Became Dislodged from Circuit Board.Visual Insp & Complete Pull Test Performed 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 ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. Efforts Underway to Define Quantity & Type of Component Parts That May Need to Be Replaced ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML18093A4721987-10-23023 October 1987 Part 21 Rept Re Calibr Gas Leakage Problem in Exo-Sensors, Inc Containment Hydrogen Analyzer Sys.Caused by Design Deficiency Associated W/Calibr Gas Subassembly.Monitoring Program to Be Maintained for Period After Sys Mods 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 ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr 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 ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr 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 ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr 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 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 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) ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr 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 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr 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 ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr 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) 1999-09-08
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JUN-01-1999 10:42 NL I NLI NUCLEAR LOGISTICS INC
- - 817 590 0484 P.01/01 June 1, 1999 NCR-73-02 Document Control Desk United States Regulatory Commission Washington, DC 20555 FAX (301).816-5151
Subject:
Interim Report of a Deviation Nuclear Logistics presents the following infonnation in accordance with 10CF.R21, §21.2l(a)(2)
. concerning a deviation, which has b~en identified.
i) Information submitted by: Mr. Aron Seiken Preside.nt Nuclear Logistics Incorporated 7450 Whitehall Street Fort Worth, TX 76118 Telephone: (817) 284-0077 Facsimile: (817) 590-0484 ii) The item with the deviation is a NLI DC Power Supply, PIN NLI-LGS-G-24-0V-R-8018.
iii) NL! has supplied these power supplies as Class lE components.
iv) The deviation, which has been identified, is premature over voltage protection actuation in a circuit specific application. The premature over voltage protection actuat~on occurred during diesel generator start up. Specifically, the premature over voltage protection actuation* occurs during diesel generator loading.
v) This issue was determined to be a deviation on April 19, 1999.
vi) These components have been supplied as safety*related components to the following facility:
- 1) Public Service Electric and Gas Company vii) To date, NLI has been unable to duplicate the premature over voltage protection actuation during laboratory testing. Data collection and additional testing is being performed to resol,.*e the 1/
deviation. If the premature over voltage protection actuation is determined to be the result of the power supply design, other NLI-L series power supplies will be tested to determine their
- ~iii!)' to similar conditions. Testing and evaluation activities will be completed on July viii) The results of testing to date has been discussed with the .cognizant personnel at the facility identified in section vi oftbis interim report.
Should you require clarification, or additional information, please contact Mr. Archie C. Bell or me.
Very T~.- Yours:_ j n_~,E~cf)~
ftR Aron Seiken President 7450 Whiteh-.11 *Fort Worth, TX 76118 Telephone (817) 284*0077
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TOTAL P.01
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0'610111999
- U.S. Nu.r Regulatory Commission Operations Cente.nt Report I
.*General Information or Other (PAR) Event# 35782
- Rep Org: NUCLEAR LOGISTICS INC Notification Date I Time: 06/01/1999 11 :07 (EDT)
Supplier: NUCLEAR LOGISTICS INC Event Date I Time: 04/19/1999 (CDT)
- Last Modification: 06/01/1999 Region: 4 Docket#:
City: FORT WORTH Agreement State: Yes County: License#:
State: TX NRC Notified by: SEIKEN (FAX) Notifications: VERN HODGE(FAX) NRR HQ Ops Officer: CHAUNCEY GOULD RICHARD CONTE R1 Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH 1
J PART 21 DEVIATION IN A NUCLEAR LOGISTICS INC (NLI) DC POWER SUPPLY.
A DEVIATION HAS BEEN IDENTIFIED IN A NLI DC POWER SUPPLY, P/N NLl-LGS-G-24-0V-R-8018 WHICH HAVE BEEN SUPPLIED AS A CLASS 1E COMPONENT, THAT ALLOWS A PREMATURE OVER VOLTAGE PROTEGllON ACTUATION TO OCCUR IN A CIRCUIT SPECIFIC APPLICATION. THIS CONDITION OCCURRED"b>URING DIESEL GENERATOR STARTUP, SPECIFICALLY DURING DIESEL GENERATOR LOADING. THIS*ISSUE W..AS DETERMINED TO BE A DEVIATION ON 4/19/99, HOWEVER, TO DATE NLI HAS NOT BEEN ABLE TO DUPLICATE THIS CONDITION DURING LABORATORY TESTING. DATA COLLECTION AND-ADDITIONAL TESTING IS BEING PERFORMED TO RESOLVE THE DEVIATION. IT THE PREMATURE OVER VOLTAGE PROTECTION ACTUATION IS DETERMINED TO BE THE RESULT OF THE POWER SUPPLY DESIGN, OTHER NLl-L SERIES POWER SUPPLIES WILL BE TESTED TO DETERMINE THEIR SUSCEPTIBILITY TO SIMILAR CONDITIONS. TESTING AND EVALUATION ACTIVITIES WILL BE COMPLETED ON 7/16/99. THESE COMPONENTS HAVE BEEN SUPPLIED AS SAFETY-RELATED COMPONENTS TO PUBLIC SERVICE ELECTRIC AND GAS COMPANY.