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-23AML20210E359 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Dresden, Oconee, Indian Point, Hope Creek, Sequoyah, Turkey Point, South Texas, Zion |
---|
Issue date: |
03/27/1997 |
---|
From: |
Jackie Jones GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
---|
To: |
NRC |
---|
References |
---|
REF-PT21-97 NUDOCS 9704010413 |
Download: ML20210E359 (5) |
|
|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers 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 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 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced 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 ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 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 B17414, Part 21 Rept Re 980116 Failure of Tachometer Transducer,Id Number TG-25-5,during Surveillance Test.Caused by Bearing Failure Which Could Cause Shaft to Seize & Break.Removed from Svc & Replaced Failed Tachometer Transducer1998-09-0303 September 1998 Part 21 Rept Re 980116 Failure of Tachometer Transducer,Id Number TG-25-5,during Surveillance Test.Caused by Bearing Failure Which Could Cause Shaft to Seize & Break.Removed from Svc & Replaced Failed Tachometer Transducer ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236Y1231998-08-0707 August 1998 Part 21 Rept Re Gas & Turbine Generator for Dedicated Emergency Power to Vital AC Buses ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed ML20236Y1571998-08-0303 August 1998 Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated 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 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247B6751998-05-0101 May 1998 Part 21 Rept Re Evaluation & Notification for RELAP4 Excessive Variability at Millstone Unit 2.Caused by Small Changes in Input to RELAP4 That Can Result in Large Changes in Calculated Peak Cladding Temp.Informed NRC of Deviation ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies 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 L-98-041, Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods1998-03-0909 March 1998 Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods ML20198E0631998-01-0707 January 1998 Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements L-97-059, Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 9802151997-11-14014 November 1997 Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 980215 ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected 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 B16531, Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair1997-07-0303 July 1997 Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20140D6581997-06-0606 June 1997 Part 21 Rept Re GE Model Ifcs Relays Procured from GE Delivered W/Loose Hardware & Unsuitable for Use at Unit 1 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML20141K7741997-04-24024 April 1997 Part 21 Rept Re Auxiliary Feedwater Check Valve Failure. Concluded Thermal Gradient Conditions Created by Flowing Cold Water Through Hot Valve Created Rapid Cooldown of Seat Ring,Allowing Ring to Displace 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 ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20135E3811997-03-0303 March 1997 Part 21 Rept Re Output Drift W/Increasing Temperature on Several RTD Amplifiers Noted During Installation of RTD by-pass Mod at Station.Action to Identify All Circuit Cards W/Affected Date Codes,Identified B16149, Part 21 Rept Re Cracked Fuse Ferrule Defects Due to Administrative Error in Ltr Detailing Commitments Re Issue. Corrected Copy of Commitments Associated W/Ltr Provided1997-01-14014 January 1997 Part 21 Rept Re Cracked Fuse Ferrule Defects Due to Administrative Error in Ltr Detailing Commitments Re Issue. Corrected Copy of Commitments Associated W/Ltr Provided ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause B16030, Part 21 Rept Re Stocked safety-related Fuses Issued from Storeroom for Installation Which Had Cracked Ferrules in Longitudinal Direction on 960911.Procurement & Warehouse Groups Completed Inspecting Fuses in Warehouse1996-12-13013 December 1996 Part 21 Rept Re Stocked safety-related Fuses Issued from Storeroom for Installation Which Had Cracked Ferrules in Longitudinal Direction on 960911.Procurement & Warehouse Groups Completed Inspecting Fuses in Warehouse ML20134N4061996-11-22022 November 1996 Part 21 Rept Re Fifteen Different Fuse Types from Three Different Mfgs Found to Have Axial Cracks Due to Brass Being Susceptible to Defect.Functional Testing Should Be Performed on Sample of Fuses ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML20112D0101996-05-30030 May 1996 Part 21 Rept Re Possible Matl Defect in Certain Stainless Steel Swagelok Tube Fittings.List of Three Addl Shipments to Nuclear Facility of Parts Included in Investigation Encl ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-014, Part 21 Rept Re Response to NRC Notice on Nonconformance. Licensee Will Direct Cognizant Personnel Reviewing Deviation or Failure to Comply for Basic Components Delivered to Customers,To Document Whether/Not Facts Indicate Evaluation1996-04-26026 April 1996 Part 21 Rept Re Response to NRC Notice on Nonconformance. Licensee Will Direct Cognizant Personnel Reviewing Deviation or Failure to Comply for Basic Components Delivered to Customers,To Document Whether/Not Facts Indicate Evaluation ML17353A6141996-02-28028 February 1996 Part 21 Rept 10CFR21-0073 Re Defect W/Voltage Adjust Potentiometer Mfg by Chicago Telephone Supply Used on NEI Peebles (Portec) Voltage Regulators at Plant.Util Updating Voltage Regulators W/Maury Instrument Corp Potentiometer 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 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092H3811995-09-12012 September 1995 Part 21 Rept Re Addl Defective Lot of 3/8-16x11/2 Hex Capscrews ASTM-A-193 Grade B7 from Which Orders Had Been Processed & Sold to Customers by Licensee 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20217F1501999-10-12012 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 ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With L-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With A99026, Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers 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 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 A99023, Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 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 ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With 1999-09-09
[Table view] |
Text
_ _ _ - _ _ _ _ _ _ - _ _ - _ _ _ . - _ _ _ _ _ _ _ _ -
, C'$X'C22 Gn LICEt6ltG 247 FBt ITH 27 '97 13:10 h CENERAL MDR0lC8i so -/oS JAarch 27,1997 NRC Operci,ons Center '
~
= = u man
'J.S. Nuclear Regulatory Commission Washington, rt C. 20555 ' -
Sub)pa 10CFR21 R9portableitem T7 IN1i D 1 ; 'i Gentlemen:
This letter is provided in compliance with the requirements of 10CFR 21.21.
The information following is in accordance with the repot ag requirements of 10CFR2121(a)(4):
i) PersonInforming the Commission:
John E. Jones 1
Sr. Vico President, Administration l
General Atomics 3550 General Atomics Court San Diego, CA 92121 l
- 11) Descriptionof thedefect in the process of performing software verification and validation (V&V) of the RM 23A Control and Display Module (part number 03575300-001), Sorrento Electronics, Inc. (SE) has determined that the Operation and Maintenance (O&M) Manual for the RM 23A may not adequately define the requirements for performing periodic surveillance of certain safety related applications.
iii) Identi5cationof thefirm:
Sorrento Electronics, Inc.
An Afbliate of General Atomics f
{$A"lMSE8Sho JE/9 010008 MlpHBPPPPNM 4
3650OtheAAL ATOMitiCOUAT,SANDi100 CA $21211194 P 4 904 88604. $AN DilGO. CA 92100 $)la t$th a6fr3000
. _ . -- . - . . - - - - . . . . - _-- ~ _ - - _- - - -. . ..
GS52022 Gn t.lCD Gltu 347 P03 iTR 27 '97 13:10 Iv) Thenatureof defect A series of diagnostics tests are used toldentify hardwaro failures which may not be dciected during normal operation. Those diagnostics tests are described in the O&M Manual and include:
a) Lamp and LED test b) Keyboard input test c) Clockinterrupt test d) Digitalinputs test e) Digitaloutputs test f) Analog outputslost The O&M Manual does not adequately emphasize the need to consider performing these tests as part of normal maintenance to declare operability in safety related applications, v) The date on which the information was obtained:
January 30,1997 vi) The number and locaton of the components.
(See Attachment 1) vil) Correc0ve action
- SE will make the individual purchasers aware of this possible problem and will revise the RM-23A Operation and Maintenance Manual E-115-1256 (Rev.1) to clarify the periodic surveinance requiren ents for the RM-23A.
viii) Advice to Purchasers:
The functions tet ted by the above diagnostics tests should be evaluated for the affect on plant safety, hiy function which affects plant safety should be I periodically tested. '
SE recommends that as a minimum, the clock interrupt test should be wrformed since the RM-23A will not schedule tasks without the interrupt acing present.
The interval between these tests should be determined by the Purchaser, 1
1
4552c22 on ucosite 247 re2 rinR 27 'rfr 23:30 if you have any questions concerning this report, please cal Dr. Keith E. Asmussen at 619455 2823 or Mr. Brian Laney at 6194554369.
Any technical questions should be addressed to Dirk Koopmin at 6194574899.
Yours Very Trt.ly,
\ q 1
- -, w; n E. Jon I Vice Pr t, Administration cc
- NRC Region IV e
9
4%?C22 CA LICD 61tG 247 rol !1nR 27 '97 13:17 Attachment 1 i
Locatlans of RM 23A's Number of RM 23A's Site innfallad in System l BeaverVaney 16 Bruce A 10 Chinshan 1 and 2 6 Dresden 2 and 3 1 Hope Creek 18 Indian Point 3 16 Kori1 and 2 6 Kuosheng 1 and 2 7 Millstone 2 1 Oconee 1,2, and 3 6 Sequoyah 1 and 2 8 South Texas 1 and 2 34 Turkey Point 3 and 4 3 Zion 1 and 2 1 a
.t GENERAL INFORMATION or OTilER EVENT NUMDER: 32033 LICENSEE: GENERAL ATOMTCS, SAN DIEGO, CA CITY: SAN DIEGO NOTIFICATION DATE: 03/27/97 REGION: 4 NOTIFICATION TIME: 15:00 (ET)
COUNTY: STATE: CA EVENT DATE:
LICENSEN: 01/30/97 AGREEMENT: Y EVENT TIME: 12 00 [PST)
DOCKET: LAST UPDATE DATE:
I 03/27/97 NOTIFICATIONS I
LEANNE !!ARRISON, R1 RDO NRC NOTIFIED BY: SilIRLEY SMITH DAVID VERRELLI, R2 RDO 11Q OPS OFFICER: DICK JOLLIFFE ROGER LANKSBURY, R3 RDO TOM STETKA, R4 RDO EMERGENCY CLASS: NOT APPLICABLE VERN llODGE NRR l
10 CFR SECTION:
CCCC 21.21 UNSPECIFIED PARAGRAPil EVENT TEXT
- 10CFR21 REPORT ON GENERAL ATOMICS RADIATION MONITOR MAINTENANCE TESTS -
SORRENTO ELECTRONICS, INC (SE), AN AFFILIATE OF GENERAL ATOMICS, DETERMINED TilAT THE OPERATIONS AND MAINTENANCE MANUAL FOR RADIATION MONITOR #RM-23A (CONTROL AND DISPLAY MODULE PART NUMBER #03575300-001) MAY NOT ADEQUATELY DEFINE Tile REQUIREMENTS FOR PERFORMING PERIODIC SURVEILLANCE TESTS OF CERTAIN SAFETY RELATED APPLICATIONS. SE IS RECOMMENDING T!!AT ADDITIONAL DIAGNOSTIC TESTS BE RUN AS PART OF NORMAL MAINTENANCE ACTIVITIES IN ORDER TO IDENTIFY !!ARDWARE FAILURES WHICH MAY NOT BE DETECTED DURING NORMAL "PERATIONS. SE IS REVISING TilEIR OPERATIONS AND MAINTENANCE MANUAL TO
'FLECT TilIS CHANGE.
GENERAL ATOMICS IS NOTIFYING TIIEIR FOLLOWING NUCLEAR CUSTOMERS:
BEAVER VALLEY, BRUCE, CilINSilAN, DRESDEN 2 & 3, liOPE CREEK, INDIAN POINT 3 KORI, KUOSl!ENG, MILL 3 TONE 2, OCONEE, SEQUOYAH, SOUTH TEXAS, TURKEY POINT 3 & 4, AND ZION.
l