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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 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 ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed 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 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 ML20198K5081998-01-0606 January 1998 Part 21 Rept Re Transient Analyses at Exposures Prior to End of Cycle.Caused by Component Defect.Notified Commonwealth Edison of Defect & Provided Revised Limits by Siemens Power Corp ML20203B3691997-12-10010 December 1997 Part 21 Rept Re Potential to Exceed Operating Limits.Cycle 8 Delayed Until Fall 1998 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 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 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 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 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 ML20134Q0801996-11-27027 November 1996 Part 21 Rept Re Deficiency of Wkm Model 70-13 Pneumatic Actuators Manufactured by Anchor Darling Valve Company Due to Incorrect Calculation of Bench Set & Supply Air Set Points.All Affected Valves Have Been Reviewed & Evaluated ML20128F5011996-10-0404 October 1996 Part 21 Rept & Deficiency Rept Re Wkm Model 70-13 Pneumatic Actuators Mfg by Anchor Darling Valve Co.All Affected Valves Being Reviewed/Evaluated & Design Changes Are Being Initiated as Required ML20117P3141996-09-11011 September 1996 Part 21 Rept Re Deficiency of GE Type RMS-9 Overcurrent Trip Device Programmers 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 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 ML20086A2751995-06-27027 June 1995 Part 21 Rept Re Several Incidents of Instrument Drift in Excess of Specified Limits for Rosemount Pressure Transmitter Model 1154SH9.Other Licensees Advised to Be Alert to Differences in Pressure Indication ML20082B5271995-03-28028 March 1995 Part 21 Rept Re Notification 9505 Automatic Switch Co Pilot Solenoid Valve Model NP8323A20V.Caused by Failures of MSIVs to Close to Asco Pilot Solenoid Valves.Subj Valves Replaced W/Valcor 3-way Solenoid Valves ML20082E1901995-03-27027 March 1995 Part 21 Rept Re Sticking of B Core Assembly to Plugnut on Automatic Switch Co Dual Solenoid Valve Model NP8323A20V. Unit 2 Valves Replaced.Unit 1 Valves Will Be Replaced ML18153B0841994-09-26026 September 1994 Suppl to 940902 Initial Part 21 Rept Re Defect W/Governor Valves Used in turbine-driven Pumps Mfg by Dresser-Rand to Formally Addresss Written 30 Day Rept Requirement of 10CFR21(c)(3)(ii) ML18153B0601994-09-0202 September 1994 Initial Part 21 Rept Re Steam Drive AFW Pump Governor Valve Mfg by Dresser-Rand.Maint Procedure to Stroke Governor Valve Stem Performed Weekly & Monitoring of Corrosion Build Up in Gland Seal Leakoff Area Performed Weekly 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 ML20069A8631994-05-17017 May 1994 Final Part 21 Rept Re Secondary Containment Isolation Techno Corp Dampers Equipped W/Parker Hannifin Air Cylinders at LaSalle County Station.All Units 1 & 2 Techno Dampers Equipped W/Parker Air Cylinders Replaced ML20070N3451994-05-0202 May 1994 Part 21 Rept Re Failures of Limit Switch Series EA740-86700 Mfg by Namco Controls Co Due to Excessive Amount of Grease on Contact Block & Contact Carrier & Wrong Matl of O-ring. Series EA740-86700 Switches Replaced w/EA740-50100 Switches ML20063D0861994-02-0202 February 1994 Part 21 Rept Re Possible Anomaly W/Namco Controls EA740 & EA750 Series Limit Switches.Investigation in Progress & Has Not Been Concluded.Vendor Will Advise NRC within Next Thirty Days Re Matter as Addl Info Becomes Available 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 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed 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 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 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 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling 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 ML18153D0811992-08-0303 August 1992 Interim Part 21 Rept Re Analysis of Klockner-Moeller Model NZM6-63,480 Volt Circuit Breakers.Initially Reported on 920701.Lever Fracture Should Be Examined to Determine If Any Cleaning Sprays or Purifying Agents Have Been Used 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 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change 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 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With 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 ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With 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 ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML20206D3331999-04-27027 April 1999 SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20 ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML20204C8141999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for LaSalle County Station,Units 1 & 2.With ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. 1999-09-30
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SO' 3 7W3 719 70 sgp GENERAL ,' ELECTRIC NUCLEAR POWER ,
1 SYSTEMS DIVISION GEN' A ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 682, (408) 925-5040 August 12, 1981
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Office of Inspection and Enforcement 'N US Nuclear Regulatory Commission Washington, DC 20555 Attention: Victor Stello, Jr., Director j
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SUBJECT:
REPORTABLE CONDITION e/
CROSBY SRV SOLEN 0 IDS -
This letter is to advise the NRC of a reportable condition per 10CFR Part 21 as reported to your office by C. A. Cameron, Manager, Safety Evaluation Programs on August 12, 1981. The condition is an incompati-bility which exists between the capability of the Crosby 6x10 and 8x10 SRV solenoids to be actuated during a 340 F LOCA condition and the worst case minimum plant available power supply voltage. The condition was judged reportable on August 11, 1981.
Attached is the report of the condition including the corrective actions to be taken. General Electric will inform the utilities that are affected by the defect and will advise them of the corrective actions to be taken. The scheduled corrective action completion dates have not yet been established. The NRC will be advised of these dates when they are established.
Very truly yours,
.. ed dd Nuclear Safety and Licensing Operation GGS:hmc/SLP516 Attachment cc: R. T. Carlson, NRC Region I J. P. O'Reilly, NRC Region II 6lC '
J. G. Keppler, NRC Region III $
V. Potapovs, NRC Region IV R. H. Enge? ken, NF': Region V g i
V. Stello, Jr., NRC (2. extra copies)
J. F. McAllister, General Electric L. S. Gifford, General' Electric g8200357 R10812' g- ADOCK 05000280 PDR
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2 CROSBY SRV SOLEN 0ID PILOT VALVE ASSEMBLY I. Description of the Condition An environmental qualification test was performed at Wyle Laboratories under GE contract on a Crosby SRV actuator and solenoid assembly to demonstrate compliance with IEEE-323-1974. The test identified that during the simulated 340 F,105 psig steam LOCA condition, the_ solenoids required 130 VDC power to be actuated. A y
separate W'le evaluation done for LaSalle showed that at least 125 VDC are required to actuate the solenoid valves for ADS appli-cation under LaSalle environmental and operating conditions. A revies of the applicable GE plant D.C. power supply specification for LaSalle and other plants utilizing the Crosby SRV solenoids in queetion specifies that the system voltage at the bus should be between 110 VDC and 135 VDC normally with an extreme low of 105 VDC during peak loading or at the end of discharge during an emergency.
Therefore, the minimum voltage available to actuate the solenoid is 105 VDC under worst case conditions, not tha required 125 VDC.
This incompatibility is applicable to all Crosby SRV's on the following plants:
Hanford 2 Zimmer 1 Susquehanna 1 TVA X-17 LaSalle 1/2 There are no Crosby valves in domestic operating plants. This condition is reportable under Part 21 because these valves had already been shipped to sites before the defect was found.
II. Safety Implications The safety implication of this condition is quite clear. If, during the extremely unlikely event that a SBA LOCA is followed by loss of off-site power and Uic ADS signal is received due to HPCS/HPCI ,
failure and the ADS fails due to low voltage, then serious degradation of the core cooling capability results.
III. Corrective Actions Recent tests performed by General Electric at Crosby Valve and Gage Company have identified the necessary criteria t assure solenoid operation at a 340 F LOCA condition with a 105 VOC power supply source applied. All assemblies manufactured and/or in the field will be inspected using the stricter acceptance criteria. Those assemblies which do not meet the acceptance criteria will be replaced.
RSB:rm:hmc/857 7/16/81