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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error 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 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 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML17292A2141996-05-0808 May 1996 Part 21 Rept Re Capscrews Supplied to Wppss by Now Defunct Cardinal Industrial Products,Lp (CIP) Having Nonconforming Hardness.Failed Lots & Any Remaining Product Found to Have Been Heat Treated by CIP Scrapped & Removed from Premises 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 ML17291A2571994-07-22022 July 1994 Part 21 Rept Re Westinghouse Containment Penetration Modules Scotchcast Strain Relief & Varglas Insulated Conductors. Replaced Six of 12 RPIS Scotchcast/Varglas Modules & Three Scotchcast/Okonite Modules During Refueling Outage (R-9) ML17291A2351994-07-15015 July 1994 Deficiency Rept Re Material Defects in Facility Containment Penetration Modules.Initially Reported on 940715.Modules Were Replaced ML17290B2001994-05-26026 May 1994 Part 21 Rept Re Automatic Switch Co Replacement Solenoid Pilot Valve Diaphragms Supplied by GE Nuclear Energy.Unusual Combination of Scram Soleniod Pilot Valve Pressure & Exhaust Diaphragm Degradation Caused Failure of Rod to Scram ML20056E9751993-08-19019 August 1993 Provides Insp Results & Safety Analysis Re Operational Amplifiers Discussed in 920917 & 23 Ltrs as Potential Safety Issue.Concludes That There Are No Safety Concerns W/Respect to Buffer Amplier Module.Ltr Not 10CFR21 Notification ML20044G5011993-05-26026 May 1993 Part 21 Rept Re Buffer Amplifier Modules Mfg by Bailey Controls Co Containing Suspect Negative Ref Power Supply Having Safety Implications.Caused by Design Error in Circuitry.Modules Would Not Result in Miscalibration ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites 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 ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B2191992-09-23023 September 1992 Suppl to Part 21 Rept Re Potential Deviation in Some Bailey Controls Co 88 Series Modules,Transmitted Via .One Module Found Incapable of Reaching 100% Output at Max Rated Load.Recommends That Circuit Board Assemblies Be Inspected 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 ML17289A8061992-08-14014 August 1992 Part 21 Rept Re Undersized Yoke Clamps in Three Anchor Darling HPCS motor-operated Valves.Clamps Located on Return Lines to Condensate Storage Tanks & Suppression Pool.Clamps Will Be Replaced by Util by 921031 ML17289A8241992-08-14014 August 1992 Part 21 Rept Re Undersized Yoke Clamps on Three HPCS motor- Operated Valves Supplied by Anchor/Darling Valve Co.Nde Will Be Performed on All Clamps to Determine If Condition Affects Valve Operability.Clamps to Be Replaced by 921031 ML17289A7991992-08-13013 August 1992 Part 21 Rept Re Limitorque Failure to Use Grade 5 Housing Cap to motor-operator Housing,Per Generic Ltr 89-10. Initially Reported on 920730.Seven GL 89-10 Category Valves Could Have Failed Due to Condition ML17289A7721992-08-0606 August 1992 Interim Part 21 Rept Re Discrepancy in Procedure Used by Siemens Nuclear Power Corp to Analyze Feedwater Controller Failure Event w/COTRANSA2 Computer Code.Initially Reported on 920709.Analysis for Cycle 8 Revised & Incorporated ML17289A7851992-07-30030 July 1992 Part 21 Rept 23965:on 920730,determined That Limitorque motor-operators Had Upper Housing Cover Cap Screws Set at 100% of Mfg Rated Thrust Which Could Fail in Svc.Caused by Installation of Grade 1 or 2 Instead of Grade 5 or 7 Screws ML17289A7521992-07-0909 July 1992 Part 21 Rept Re Discrepancy in Procedure Used to Analyze Feedwater Controller Failure Event Using COTRANSA2 Code. Initially Reported by Siemens Nuclear Power Corp on 920617. Caused by Transient Analysis Error ML17289A8591992-07-0808 July 1992 Part 21 Rept Re Delta CPR Transient Analysis Error for Feedwater Controller Failure Event Performed by Siemens Nuclear Power Corp.Feedwater Transient Actually Occurred on 911119.Fuel Cladding Failure Not Possible ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML17286B2501991-11-14014 November 1991 Part 21 Rept Re Potential Deficiency W/Asl Dry Type Transformers.Initially Reported on 910610.Recommends Issue Be Pursued W/Abb Since Westinghouse Did Not Have Necessary Technical Info or Expertise to Identify Cause or Solution ML20079B8591991-06-10010 June 1991 Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating GO2-89-144, Part 21 Rept Re Defect in Fault Tripping Design for Class 1E safety-related 480 Volt Divs 1 & 2 Ac Power Distribution Sys for Motor Control Ctrs.Caused by Improperly Designed Volt Electrical Distribution Sys.Circuit Breakers Replaced1989-08-21021 August 1989 Part 21 Rept Re Defect in Fault Tripping Design for Class 1E safety-related 480 Volt Divs 1 & 2 Ac Power Distribution Sys for Motor Control Ctrs.Caused by Improperly Designed Volt Electrical Distribution Sys.Circuit Breakers Replaced ML17285A5001989-06-0202 June 1989 Part 21 Rept Re Defect Discovered in Valve Motor Operator of RCIC Inboard Containment Isolation Valve RCIC-V-63.Upper Housing Cover Will Be Machined to Remove Excess Matl to Provide Required Recess ML17285A4771989-05-19019 May 1989 Part 21 Rept Re Defects in Target Rock Actuator Kits (Part 300562-1).Initially Reported on 890516.Defects Noted in Cold Solder Condition,Insufficient Solder Joints & Failed Solder Joints.Defective Kits Returned to Mfg for Repair ML17285A4321989-04-26026 April 1989 Part 21 Rept Re Defect in Limitorque Valve Motor Operator Model SMB-2 W/Soft Worm Shaft Clutch Gear Assembly.Caused by Failure to Install Split Spacer of Worm Shaft Clutch Gear assembly.Safety-related Valves Manually Operated 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 ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20212A5601986-12-17017 December 1986 Part 21 Rept Re Amplified Response Spectra.Applicable Floor & Wall Mounted safety-related Equipment Reviewed & as-built Geometry & Mass of Seismic Category I Structures Compared to Original Use in Generating Amplified Response Spectra ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing 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 ML20210F4741986-09-16016 September 1986 Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List 1999-01-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing 1999-09-30
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PSC 58-79 Subj. Will J LdC RM Date PPiLII:1!;ATsY SAFETY CO*iCERN PIPOP.T ECE!SER 13, 1979 gn ... ....-- - .
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Attached are the findings of Licensing's evaluation of a prelicinary safety f, concern involving visual liner.r defects in an AS*-2 III. Class 2 core flooding syste.1 isolation valve ac.d unacceptable indications in six (6) AS!E III.
Class 1 decay heat syste . isolation valves that were canufactured by WK:t Division of ACF Indast:-fes for the WPPSS contract. The prrhlem can be
- su carized as follo.<s. J E,
The visual linear defects in the core flooding systes isolation valve were discovered by WG when the valve'was returned to then by VPPSS at the direction
_ of SEi for internal stifef vahe rework. The unacceptable indications in the decay syster. isolatico valves were discovered by WPPSS during en ASME Section XI ^
^ preservice inspection. These valves had been previously deeced acceptable '
i ,
by W m. S&W and WPPSS. '
- s Licensing's conclusions in regard to this concern are that it is reportable y;
-t under the requirerents of 10 CT. 21 since significant defects exist in a core c' flood isolation vahe that is a cc:.:>onent desiga.ed to be used to ::itigate the p.
consecuerces of accidents that could result in potential offsite exposure, and ,
, that defects may exist in six (6) decay heat syste= isolation valves that are [
i j part of the reacter coolant pressure bs.:ndary. Licensing has received the s ccocurrence of the !'ar. agers of Engir.eering and Quality f.s urance for this E evalua tion.
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- The fo11Ning subsequent actior.s are ro.e required
- 1. You are requested to indicate the tihe and date of receipt of this . _
se:.crandum and sign on the space pr3vided belod; please return the copy "-
of the signed ce=o to re.
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- 2. Licensing, per a;reeme.t with WP?SS, will report this concern by telecon >O l to the fRC and will follcw with a written re; ort to the Comissico within
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five days of that no.tification.
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Delt. ExfL Forin N U B307060528 791213 NV --
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cc: E. V. DeCarli G. O. Geissler R. E. Ham E. A. Wo.::ack J. D. Agar
~ B. D. !!elson D Mars R. E. Wascher B. A. Karrasch W. A. Cobb E. J. Domaleski B. B. Cardwell K. R. Ellison D. E. Lee L. .
G. D. Quale D. H. Roy D. W. Berger J m
H. Honig J. McFarland J. C. Deddens
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D. C. Winterich G. M. Olds G. J. Brazill .
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D. W. LaSalle E. G. Ward '
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- 9 P. G. Perry R. R. Steinke
.7 R. E. Kosiba D. L. Allison T. L. Baldvin 9.?
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This report evaluates the concern that them r.)y be significant n som defects i t
WYJ! valves supplied to t*FPSS that am used to assure the integrity of th c e reector coolant pressure bour.dary er citigate the consequences of an accident that b'
- could result in potential offsite exposures.
This rerort presents the conclusion that this cencern is reportable under the requirements of 10 CFR 21 .
Description o' Concern ;
Two linear cracks were noted on the inside of the valve body casting of a 14" x 12" core flooding syste:s isolation valve which had been returned; to manufacturer by WPPSS at EW Co. direction for rework on an internal relief valve (see attached sketch).
ACF Industries in Houston. Texas.This valve was canufactured by Wrfi Divisio WK4 reports that three other core flooding system isolction valves r.ar.ufactured for ETPSS were visually inspected and no cracks were found.
They also report that the valve body, with the visual defects, was the only one made from heat !E0321A. and that the celt log heat reports were acceptable. -
. In addition to the core flooding valve. WPPSS has reported that the preservic L inspection per Section II of the AS!E Ccde idantified five decay systers -
isolation valves to have visual indications in the valve body inlet and outlet condui ts. g
" These five valves and one additional decay heat systen isolation valve showed unacceptable indications per Sections 111 and XI of the ASE [ C when penetrant tested, ;
a -
These valves are intended for use in the decay heat systen. are part of the coolant pressure bour. dan and are sir.ilar in design and construction to the core flooding systen isolation valves. .
The cort flooding syste= isolation valves are ASE Ill Class 2 ar.d the decay heat syste isol tion valves are ASE !!! Class 1.
At this tice. the cause and extent of the defects in the core ficod isolation valve and the ir.dications in the decay heat valves are g.
not fully knoen. .
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Forty-eight (43) KC1 valves have been canufactured to date, 20 for WPPSS Bi lYA, 2 for PAS!!Y and 14 for PCE, but no WTJ: valves t.cm supplied by D5'1 for
, 4 for
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operating plants.
A list of the valves with ap:>amnt defects is attached. ~f Q~
Reportability Q
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While neither the extent nor the cause of these defects and indi -
presently determined, there appears to be sufficient eviderice to conclude that '
y a significant defect exists in a core flooding system coyonent dasigned to be used to mitigate the consequance of accidents that could result in potential ,
offsite exposure and that defects cay exist in decay heat systen co::ponents used to assure the integrity of the reactor coolant pressure boundary. There-fore, the concern is judged reportable under the requirecents of 10 CFR 21 .
follo.*un Action Plan i I
BW Co. personnel working with UPPSS and WrJi will define and initiate progr i.
for the two cases (the WPPSS reported Di Valve case and the WC1 reported CF i
valve dnd case) deterDine to determine acceptable fly.es. the extent and cause of these indicati -
These prograc5 should also resolve the questica of whether the two cases are related and pmvide assurance of accept-4 ability of the recaining valves supplied by Wei for su contracts. B W will -
advise TVA, PAS!!Y and PGE of this concern and will keep them advised of the progress of the further investigations and the selected fixes. *
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I WKM Valves with Possible Defects '
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Valve Valve llI Item
_ Class Desinnation i Sys tem / Plant Defect Foted By ,
i Decay Heat Case *! t Removal System Class 1 DH - V12A )
Discovend DHR/ Unit 1 Visual and PT Isolation Valves by WPPSS DH - V120 DiR/ Unit 1 PT ij ,
Class 1 4 0H - V11B ;
fj D4R/ Unit 4 Visual and PT V11A DIR/ Unit 4 Visual and PT g
V12A DIR/ Unit 4 Visual and PT-
' V12B DIR/ Unit 4
. Visual and PT .
Core Flooding Case !! Class 2 System Isolation 4 CF - 1A CF/ Unit 4 i
Valves Discovered Visual Ifnear ; ,
by WKM e cracks plus '
radiography ,
WKM Total */alve PASNY 2 - All decay heat cooler outlet control valves Count-Backlog TVA 4 - All deccy heat cooler outlet control valves ,3 Contracts PGE 14 - 12 isolation valves + 2 decay heat enoler outlet control valves WPPSS 28 - 24 isolation valves + 4' decay heat cooler outlet control valves bWXMValves h
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