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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 ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 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 ML20127P1271992-12-11011 December 1992 Part 21 Rept Re Possibility That Addl Steel & Lead of Figure 2 Would Attenuate 80 Kev Photopeak of Xe-133 Resulting in Failure to Detect Concentration of Xe 102 Microcurie/Cc Range.Schematic Encl ML20127P1101992-11-25025 November 1992 Part 21 Rept Re Calibr,Wind Tunnel for Model 8500 Thermo Anemometer Out of Spec.No New Units Sold to Licensees within Past 12 Months.Range of Possible Calibr Errors Out of Spec Is 3% to 20%.Full Rept Will Be Submitted 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 ML20059B9191990-08-21021 August 1990 Part 21 Rept Re Defects in SA-194 Grade 6 Check Valve Bonnet Nuts Supplied to Westinghouse by Copes-Vulcan.On 900316 Discharge Check Valve Bonnet Found Cracked During Routine Maint.All Bonnet Nuts for Subj Valves 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 ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified 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 ML20247Q9241989-05-26026 May 1989 Part 21 Rept 89-01 Re Containment Electrical Penetration Assemblies Supplied by Bunker Ramo.Design or Mfg Const Deficiencies Could Have Created Substantial Safety Hazards. Integrity Checks Conducted to Identify Inadequate Crimps 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 ML20245B8701989-04-21021 April 1989 Deficiency & Part 21 Rept Re Degradation of Nonmetallic Components & Sludge Formation in Lubricating Oil.Initially Reported on 890327.Degradation of Nonmetallic Parts & Fouled Bearings Evaluated 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 ML20236P0061987-11-13013 November 1987 Final Part 21 & Deficiency Rept Re Failure of LPSI Pump When Energized.Initially Reported on 840523.Results of C-E Analytical & Test Program Showed That Excessive Shaft Deflection Eliminated by Use of Larger Diameter Motor Shaft ML20214M6471987-05-27027 May 1987 Final Deficiency Rept NY-QA-8 Re Atwood & Morrill Natural Frequency ASME III Active Valves,Identified During Ebasco Engineering Review.Initially Reported on 870515.Valves Will Be Reanalyzed & Modified.Not Reportable Per 10CFR50.55(e) ML20214E4681987-05-15015 May 1987 Deficiency Rept Re Natural Frequency of ASME III Active Valves.Initially Reported on 870413.Interim/final Rept Will Be Submitted by 870527 ML20212B5121986-12-19019 December 1986 Part 21 Rept 86-01 Re Peerless-Winsmith Nuclear Grade Dc Motors.Sleeving Sys Will Be Developed & Applied Over Existing Lead Wire.Evaluation of Capability of Sleeved Lead Wire Anticipated by Third Quarter 1987 ML20207F1031986-12-18018 December 1986 Final Deficiency Rept Re Four Elgar Corp Static Uninterruptible Power Supply Units That Could Potentially Result in Failure of Class 1E 120-volt Vital Ac Bus. Condition Not Reportable Per 10CFR50.55(e) 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 ML20214W7711986-11-26026 November 1986 Interim Deficiency Rept Re Uninterruptible Power Supply Assembly Deficiencies.Initially Reported on 860708. Final Rept Will Be Provided by 870116 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 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 ML20210F8701999-07-22022 July 1999 Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar 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 ML20209C6531999-07-0606 July 1999 Rev 8 to Defueled SAR, for Trojan Nuclear Plant 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 ML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML20207G9881999-03-0303 March 1999 Rev 6 to Trojan Nuclear Plant Decommissioning Plan ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML20207J0781999-02-28028 February 1999 Update to Trojan ISFSI Sar ML20202G4511999-02-0202 February 1999 Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML20202C8081999-01-22022 January 1999 Safety Evaluation Supporting Order Terminating Construction Permit CPPR-154 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 ML20207C6981998-12-31031 December 1998 1998 Annual Rept for Trojan Nuclear Plant. with ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML20195J2501998-11-17017 November 1998 Rev 7 to Trojan Nuclear Plant Defueled Sar ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa 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 ML20155E0411998-10-27027 October 1998 Amend 7 to Quality-Related List Classification Criteria for Tnp ML20154R4121998-10-0202 October 1998 Requests Commission Approval,By Negative Consent,For Staff to Grant Two Specific Exemptions from Package Test Requirement Specified in 10CFR71 for Trojan Reactor Vessel Package & to Authorize one-time Transport for Disposal 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 ML20237B6121998-08-13013 August 1998 Revised Trojan Reactor Vessel Package Sar ML20151W5471998-08-13013 August 1998 Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant ML20236Y2691998-08-0808 August 1998 Revised Trojan Rv Package Sar 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 1999-09-30
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PART 21 IK"ITIFICATIQ'It(O, ~>>"l-. G~G COPg~y [gq Gabm:g &leap, WTE 0; tZaR DXKET NP,'6- qq Moo Sl,(6%> ~A-3:lg DhiK DISTRIBUTED Cl Are . ORIGINL REPORT X SIIPPLEI"H<ARY -:
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PRELIMINARY BfALUATION OF THE'ATlACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLOMJP AS SHORN BELOW:
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l3abcock ccVlilt..ox tluclear Power Generation Oivision a Mcoermott company 3315 Old Forest Road P.O. Box 1260 Lynchburg. Virginia 24505 (804) 384 5111 January 9, 1981 r~ "-".tq 6>>> 0t;o Hr. Victor Stello, Director Qg~Qtg Office of Inspection and Enforcement Go- G>g United States Nuclear Regulatory Commission 4- GZ Washington, D. C. 20555
Dear Hr. Stello:
lt 5
Pursuant to the requirements of 10CFRgl this report, in three copies, is made concerning valves supplied by Control Components International (CCI),
Irvine, California, for use as makeup flow control valves on Washington Public Power Supply System (WPPSS) and Portland General Electric (PGE) contracts which will not supply 2 gpm flow when in the closed position as requirsd by B5W specification. The function of this valve is to supply cold (n120 F) borated or demineralized water as makeup to the reactor coolant system (RCS) through a nozzle in the cold leg. This nozzle is one of four that is also used to supply high pressure injection for emergency core cooling in a LOCA situation.
The concern is that, without this flow in the closed position, normal transient operation could cause thermal cycling that would exceed the stress limits of this nozzle over forty year plant life. Failure of this nozzle could result in a LOCA or in a LOCA situation result in a partial loss of high pressure i n jecti on capaci ty.
These valves are used in the Makeup and Purification systems for the NPPSS contract, two valves, one per plant, designated MU-V46; and for PGE contract, one valve, designated HU-Y46. They are not used for this application in any operating plant or other plant under construction.
The cause of this concern is the inability of the valve to supply the specified flow in the closed position. Corrective action consists of:
- l. Notification of the affected licensees of this concern.
- 2. Initiation of a program to determine the best method to provide the required 2 gpm flow when the valve is closed. Both use of a different or revised valve design or provision of an external bypass line are being considered. Corrective action will be considered complete when the selected method to restore this specified 2 gpm flow is implemented on the affected contracts.
BBl3cocl( &Yi'ilcox ter. Victor Stello, NRC January 8, 1981 Hr. D. E. Guilbert, Vice President, Nuclear Power Generation Division of Babcock 5 l<i lcox Company was informed of this reportable concern on January 5, 1981.
This letter confirms our telephone conversation of January 6, 1981 on the subject with hir. H. R. Nills of your office.
V trul vours
. H. Tayl bianager, Licensing JHT:vp cc: R. B. Borsum D. E. Guilbert
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