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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 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 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 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 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 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 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 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 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 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 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 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 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 ML20195E4881986-05-23023 May 1986 Part 21 Rept Re Potential Failure of Ite/Gould Disconnect Switch,Type 7860 Ds Series.Instructions for Verification of Proper Operation of Switches Included in Notification to Plants.New Switches Available by 860901 ML20205L0921986-03-21021 March 1986 Part 21 Rept Re Throttling Requirements & Capabilities of HPI Valves Supplied to Bellefonte,Units 1 & 2 & Washington Nuclear Project.Utils Notified & B&W Suggested Listed Options for Resolving Concern ML20141F6111986-01-0303 January 1986 Interim Part 21 Rept Re Error in Computer Program Used in Analysis of Component Supports.Nuclear Pipe Support Design Guidelines Revised to Require Conversion to Another Computer Program.Final Rept by 860307 ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed ML20113D7061985-01-15015 January 1985 Final Part 21 Rept Re Defective Valve Operators.Initially Reported on 841030.Control Valve Failures Resulted from Hydraulic Fluid Contamination & Improper Maint Procedures Which Allowed Aeration of Hydraulic Fluid ML20084K0111984-05-0303 May 1984 Potential Part 21 & Deficiency Rept 84-04 Re Failure to Protect Certain Cables in Dedicated Shutdown Sys.Wppss Presently Design Control Authority.Procedures Revised GO2-83-117, Final Deficiency Rept,Condition 307 Re Target Rock Isolation Valve 82M-002 on Loop B Not Closing When Deenergized. Initially Reported on 831219.Twelve Valves Disassembled, Readjusted & Reinstalled Under Vendor Supervision1983-12-20020 December 1983 Final Deficiency Rept,Condition 307 Re Target Rock Isolation Valve 82M-002 on Loop B Not Closing When Deenergized. Initially Reported on 831219.Twelve Valves Disassembled, Readjusted & Reinstalled Under Vendor Supervision ML20083G6981983-12-20020 December 1983 Revised Final Deficiency Rept,Condition 260 Re Insufficient Flow to HXs in Standby Svc Water Loops a & B.B&R Evaluating Design Error.Also Reported Per Part 21 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 ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr 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 ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr 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. 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 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 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 ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr 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 ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
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Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 Docket No. 50-397 September 9, 1983 G02-83-820 O
Mr. J. B. Martin 9, n
Regional Administrator E 40.
C U.S. Nuclear Regulatory Commission S .: ;E Region V .
~G 1450 Maria Lane, Suite 210 '
3 Walnut Creek, California 94596 e C ',
Subject:
NUCLEAR PROJECT NO. 2 10CFR50.55(e) REPORTABLE CONDITION #269 BECHTEL POWER CORPORATION REPAIR OF WRONG WELD AREA
References:
- 1) Telecon QA2-83-129, dated July 5, 1983, C.S. Carlisle to J. Elin.
- 2) Letter #G02-83-671, dated July 28, 1983, C.S. Carlisle to J.B. Martin, same subject.
In accordance with the provisions of 10CFR50.55(e), your office was informed, by telephone, of the above subject condition on July 5, 1983. The attachment provides the' Project's final report on this condition. Please note that this report also responds to item of noncompliance 397/83-38-08 of the same subject.
If you have any questions, please contact Roger Johnson, WNP-2 Project QA Manager at (509) 377-2501, extension 2712.
C Program Director, WNP-2 LCF/kd
Attachment:
As stated cc: W.S. Chin, BPA N.D. Lewis, EFSEC A. Toth, NRC Resident Inspector Document Control Desk, NRC i
4 8309260317 830909 PDR ADOCK 05000397 \\
S PDR --
WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 DOCKET N0. 50-397 LICENSE NO. CPPR-93 10CFR50.55(e) CONDITI0il #269 BECHTEL REPAIR OF WRONG WELD AREA FINAL REPORT Description of Deficiency Weld RHR-851-18.19, 12ARl-FW12A was originally aade, radiographed, repaired, reradiographed and accepted by WBG, the previous aechanical contractor. As a special task under the WitP-2 Quality Verification Prograra, Bechtel perforced a 100% review of the WBG weld radiographs. Upon reinterpretation of the W3G radiographs for weld RHR-851-18.19, 12ARl-FW12A, Bechtel concluded that a re-jectable indication had been overlooked, and further repairs were necessary to aeet Code rec,tireaents.
A nonconforaance report was prepared, the appropriate weld papers were issued, and the weld was excavated, repair welded, reradiographed and accepted by Bech-tel. However, because of an error in determining the location of the defect from the weld station markers on the WBG radiograph, Bechtel excavated, repair welded and reradiographed the wrong area. This layout error, which resulted in repairing and radiographing the wrong area, was not detected by Bechtel when they reviewed and accepted the repair radiographs. This deficiency was due to a failure to compare the original WBG fila, which Sechtel had found unacceptable, with the Bechtel repair film which was accepted. This error was discoveredo'y the NRC CAT inspector by comparing the original filra with the repair fila when he performed a randora check of 3echtel weld repair radio-graphs.
Analysis of Safety Implication Two of the 14 ceficient repair welds were in non-safety related Quclity Class II, AJSI 331.1 ;,iping systeras. Of the remaining 12 Quality Class I welds, two of the deficiencies were due to lack of complete fila coverage. One of these was completely cut out because of an isoaetric drawing nodification,-
snd the other one was free of weld flaws.
A linear elastic fracture mechanics analysis has aeen performed on the rac.io-graphic fic.: indicctions in the reasining 10 Qucli;y Cicss : ,.;e .:lds using the methodology of AS..E XI, Appendix A. This analysis snows taat the stress bre lower than the conservatively estimateo critical intensity values of KIc fcctors (120 ksi (KI) 5 ) and Kla (100ksi EASici2 ). XI, IUS-3512 provides the following acceptance criteria cased upon applied stress intensity factors:
- 1. For noraal conditions: KI x JIO e. Kla
- 2. For emergency and faulted conditions: KIx[24 K Ic As shown by the data presented in Table 2, the stress intensity factors for all weld flaws raultiplied by 10 are well below the conservatively estimated l critical value of 100 ksi in for KI . Frora this it can be conservatively concludedthathadtheweldrepaird$ficienciesgoneundetected,theywould not have adversely affected the safety of operations of the nuclear power plant at any time throughout the expected lifetime of the plant.
FR269 - Page 2 of 4 Based upon the above information, it is concluded that the deficiency is not reportable under the rules of 10CFR50.55(e).
Cause of Deficiency The above described deficiency can be directly traced to a failure to compare the repair radiographs with the original radiographs to assure that the correct area was repaired, and the originally rejected discontinuity was satisfactorily removed.
The review, interpretation and acceptance of radiographs is a Bechtel QC respon-sibility. The governing procedures used by Bechtel QC for reviewing radiographs were RT-ASME, Rev. O and QCI W-1.00A. Neither of these procedures specifically state that the original film shall be compared with the repair film when review-ing and accepting radiographs for weld repairs. This procedure inadequacy is believed to be the underlying root cause responsible for the deficiency.
Corrective Action Weld RHR-851-18.19, 12AR1-FW12A, was documented on NCR #21688, repair welded (QCIR W-100A-6974), reradiographed (NDE Report #4073) and finally accepted on 6/24/83.
In addition to correcting the one specific deficiency identified on NCR-21688, Bechtel performed a 100% review of all other welds which were repaired, radio-graphed and accepted without comparing the rejected film against the repair film to confirm that the originally rejected defects were removed. From a complete review of all Bechtel RT reports, it was determined that Bechtel made and accepted 297 weld repairs without comparing the original film with the repair film. For each of these 297 welds, the necessary comparisons were made and it was determined that 13 additional weld repairs were incorrectly accepted. A complete description of these 13 deficient repair welds plus the one original weld repair deficiency discovered by the NRC Construction Apprai-sal Team is presented in Table 1.
The data in Table 1 shows that the deficiencies for all 14 welds have been satisfactorily resolved. The one ASME III/l and three of the four ASHE III/2 welds were successfully repaired and reradiographed. The one remaining ASr1E III/2 weld which did not have full film coverage of the repair, has been re-radiographed and accepted.
Six cf the seven ASME III/3 welds, which do not require radiographic examin-ation, successfully passed the Code required surface NDE (liquid penetrant) examination. The one remaining ASME III/3 weld was completely cut out due to an isometric drawing modification. These seven ASME III/3 welds were origin-ally radiographed as a part of the project welder performance evaluation program which was outside of the design specification and Code requirements. Fracture 4
Mechanics analysis using the methodology of ASHE XI, Appendix A, shows that the radiographic indications are within the acceptable limits for the design service conditions.
The remaining two welds were Quality Class II, ANSI B31.1. These two welds d
were successfully repaired and reradiographed.
FR269 - Page 3 of 4 With one exception, the failure to identify deficient weld repairs for all 14 items was due to not comparing the original film with the repair film.
The one exception was item 14 in Table 1, classified as category D (Weld FPC-669-1.7-2AFW2A). The error in this case was unrelated to comparing the origi-nal film with the repair film, but was simply due to a misinterpretation of or failure to identify rejectable indications on the repair radiographs. Fur-ther corrective action was taken to resolve this single case of a radiographic film interpretation error.
The radiographs for a sample of 61 original production welds was selected from a total population of 604 welds reviewed and accepted by the same Level II RT technician who made the interpretation error on repair weld FPC-669-1.7-2A FW2A. All of the film for the 61 sample welds was re-reviewed by Bechtel Level II or Level III RT technicians. The' radiographs for 60 of the 61 welds were found to have been correctly interpreted. One radiograph for one of'the welds was noted by the original Level II interpreter as containing borderline but acceptable porosity. Upon re-review by a Level III interpreter, it was deter-mined that although the original Level II interpreter had correctly identified the indication as porosity, he apparently made a computation error in measuring its size, calculating the area and comparing it to the code allowable limits.
What the original Level II interpreter had noted as borderline porosity-accept-able, was in fact borderline porosity-unacceptable to ASME Section III require-ments. This particular weld, EDR-066-11.17-FW2, has subsequently been reclassi-fied as Quality Class II, ANSI B31.1 which is not safety significant and does not require radiographic examination.
All remaining RT reports for the 543 other welds accepted by the same Level II interpreter were then reviewed to see if he had made any other borderline acceptable notations. Fot+ additional RT reports were found with this notation and the corresponding filh. was re-reviewed oy a Level III technician. The radiographs for all four of these RT reports were found to have been correctly interpreted and dispositioned by the original Level II interpreter.
Action to Prevent Recurrence The procedure inadequacy identified as the underlying root cause of the defi-ciency has been corrected by issuing Administrative Instruction #27, dated August 16, 1983, to supplement Bechtel procedure RT-ASi4E, Rev. O. This Adminis-trative Instruction contains the following specific provisions to prevent recur-rence of the described deficiency.
- 1. Repair weld film must be compared to the original rejectea film for area of coverage, number of defects and original defect removal.
- 2. For radiographic rejects, the Bechtel Level II interpreter must make a transparency of the rejected film showing the weld identification, the area of the weld requiring repair, and the location and type of defects to be removed. This transparency is given to the welding engineer respon-
! sible for making the repair to minimize layout errors which could result in repairing the wrong weld area.
- 3. Radiographic film for rejected welds is maintained in a suspense file by the Bechtel NDE group until repairs are completed so that the original film is readily available for comparison with the repair film.
FR269 - Page 4 of 4 A training session covering Administrative Instruction #27 was conducted by a 3echtel Level III technician and attended by all WNP-2 Bechtel Level II film interpreters on August 17, 1983.
It is believed the above described actions will prevent recurrence of the defi-ciency on the WNP-2 Project.
.- t T/8.E 1 IMRECTLY ACCEPTED ELD REPAIRS ,,
REPAIR /
ITEM CATE- ISO WELD /&E FREA tG REWmK TUTH GORY PU4ER f1MER CLASS REJECTED DESGIPTION fUTER DISPOSITION CLW LETE REWRKS 1 A PJR-851 18.19 12/R1FW12A 2 1-1/2" to 3-1/2" Cmcavity 21688 Repair 06/24/83 tRC CAT team audit findira 18" Concavity 21" Incorplete Fusion 2 A RFW-419-3 12-1PW12 1 65" - 66" Slag Inclusion 21827 Reair 03/05/83 3 B RlR-899 39.44 FK20R1 2 1-2 Coverage N/A Reshoot 07/16/83 Insufficient film coverage of mpair area. Reshot T.
4 B FPC-fG 1.4 2FK2 3 0-9 Coverage N/A Cut out N/A Insufficient film coverage of repair area. Pipe was cut oJt due to iso podificatims. Reshot not mquired.
5 C RlR-1968-5 P417R1 2 2-3 Incamlete 21767 Repair 03/09/83 Penetration 6 C FPC-4444-1 W120R1 3 0-1 Incomlete Fusim 21768 Accept N/A Surface NDE and fractum rmchanics as-is acceptable.
7 C FPC-fG 10.12 3FW3R1 3 1-4 Incamlete 21766 Accept N/A Surface TOE and fracture mrrhanics Pemtration as-is acceptable.
25-27, 2S-31 Incamlete Fusion 8 C FPC-670 1.2 4/MA 3 22 Incamlete Fusion 21824 Accept N/A Surface t0E and fractum rochanics as-is acceptable.
9 C FPC-687 7.13 6FM 3 1-3 Incomlete Fusim 21824 Accept N/A Surface NDE and fractum nochanics as-is acceptable.
CATEGORY DEFINITIONS:
A. Wrong ama mpaired and radiographed - rejectable indications not roted due to failum to camare film B. Insufficient film coveram of repainxi area not noted due to failure to camare film.
C. Correct ama mpaired md radiographed - rejectable indications mt roted dJe to failure to comare film.
D. Cormct area repaimi and radiographed - interpmtatim error made in myiewiry repair film.
Page 1 of 2
TABLE 1 (CmTIPUED) -
INCORRECTLV ACCEPT 8 WELD REPAIRS ',,
REPAIR /
ITEM CATE- 150 WELD ASif /REA N01 N01 Rt M
- tOER GORY TU4ER fGFER CLASS REJECTED DES 0llPTION fuller DISPOSITIm COTLETE REFAKS
- 10 C FPC-6 0 1.6 4-1R1RM-1 3 8 Incomlete Fusion 21824 fccept N/A Surfaco TOE and fractum trechanics as-is ir.ceptable.
11 C OG-783 15.21 IFW1 N/A 11-12 Slag Inclusion N/A Repair 08/03/83 RiSI 101.1 - Quality Class II 14,17-19 Incamlete Fusion Reoair acceptable.
12 C OG-783 12.14 2FW2 N/A 16 Incomlete Fusion N/A Repair 07/27/83 ANSI B31.1 - Quality Class II Repair acceptable.
13 C W CS-629 1.4 16AFW16A 2 2-5 Inco mlete Fusion 21826 Repair 08/09/83
, 14 0 FPC-699 1.7 2AFW2A 3 12 Incomlete Fusion 21824 Accept N/A Surface TDE and fractum mechanics as-is acceptable.
j 4
1 1 .
i t
i I l CATEGORY DEFINITIONS:
l A. Wmng ama mpaired and radiographed - mjectable indications not noted d>e to failum to comare film i B. Insufficient film coverage of mpaired ama not noted due to failum to camare film.
] C. Correct area mpaired aid radiographed - mjectable indications not noted due to failure to camare film.
- D. Correct area mpaimd and radiographed - interpmtation errcr made in myiewing repair film.
t l Page 2 of 2 I
i 1
TABLE 2 .
FPACREE KOWilG NRYSIS DATA ITEM tUPER 150 PU M WELD tU M PIPE WLL DESIGN DESIGN DINETER THIO <tESS PRESSLRE TDP
$ k It01 CATION It0lCATION LEtGTH DEPm KI /lU x KI fMTERIAL (inch) (irch) (psig) (F) (ksi) (ksi) (inch) (inch) (ksi/iii) (ksi /iii) 1 RfE-851 18.19 12/R1FW12A 14 0.375 500 480* 1.9 32 0.5 0.06 14.3 45 A106-B Pipe te A106-8 Pipe 2 RFW-419-3 12-1FW12 24 1.812 1300 575* 4.3 32 0.625 0.06 16.9 53 Al % B Pipe to A352 WCB Valve 3 RFR-899 39.44 FW20R1 '#LD GLY REQUIRED R4 /0DITI0th RADIOGRAPH TD PROVIDE 01PLETE UNER/E. TOT SB11TTED FOR FRffTLRE EDW115 NRYSIS AS RADIOTAPH SHOWED to DEFECTS.
4 FPC-605 1.4 2FK2 WELD Clrr QJT DLE TD PIPItG E001FICATIONS fDT SLB4ITTED FCR FRACTl0E KOMNICS REYSIS AS DIS 01EPRD WE LAD < OF 01PLETE FIU4 (DVER/E TOT ELD FLAWS.
5 RfR-1968-5 FW17R1 2 0.218 125 480* 0.3 36 0.125 0.06 7.4 23 Al % B Pipe to A234 W[P Eltov 6 FPC-4444-1 W120R1 2 0.218 150 175* 0.3 36 0.125 0.06 13.3 42 Al % B Pipe to A231 WBP Eltov 7 FPC-605 10.12 3FW3R1 10 0.365 220 175* 1.5 36 0.125 0.06 7.8 25 A106-B Pipe to 1.5 0.06 18.5 59 A234 WBP Eltov 1.75 0.06 20.4 64 8 FPC-670 1.2 4AFW1A 10 0.165 150 175* 2.3 30 0.563 0.06 12.5 40 A312-T301 Pipe to A312-T304 Pipe 9 FPC-687 7.13 6FW6 10 0.365 150 175* 1.0 36 0.375 0.06 14.5 46 A106-B Pipe to 0.125 0.06 7.6 24 A234 WPB Eltov 10 FPC-640 1.6 4-1RlFWi-1 8 0.322 150 175* 0.9 32 0.125 0.06 7.7 24 A106-8 Pipe to A105 Valve Page 1 of 2 .
TABLE 2 (OJNTItOED) .-
FPACTIEE K0W4ICS #RYSIS DATA '.*
ITD1 tdM'IR ISO fU43ER WELD PO EER PIPE 1RL DI/MTER THID K'SS DESIGN PRESSLRE DESIGN TEhP 4 4 It0ICATIQ1 It0lCATI0f4 LEtGTH K1 /lU x KI OEPTH MTERI/L -
(inch) (inch) (psig) (F) (ksi) (ksi) (inch) (irch) (ksi/IR) (ksi/I5) 11 OG-783 15.21 IFK1 QRITY CLASS II t0T SE11TTED Fm FRACRRE K0W4ICS RRYSIS 12 OG-783 12.14 2FW2 QRITY CLASS II t0T SUBMITTED Fm FRACTtRE KCHANICS #RYSIS 13 IPCS-629 1.4 16AFW16A 24 0.375 100 212* 1.6 32 0.5 0.06 14.1 45 A106-B Pipe to A352 WCB Valve 14 FPC-669 1.7 2AFW2A 6 0.134 150 175* 1.7 30 0.219 0.06 11.6 37 A312-T304 Pipe to 0.25 .0.06 11.6 37 A403-T304 Eltxx -
0.188 0.06 11.1 35 Page 2 of 2 .