Part 21 Rept Re Existence of Nonconservative Assumption in Cold Shutdown Design Basis Boron Dilution Accident Analysis in Fsar.Caused by Use of Incorrect Sys Vol.Review Will Be Performed to Identify & Analyze Addl AccidentsML19320D195 |
Person / Time |
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Site: |
Surry, North Anna |
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Issue date: |
07/02/1980 |
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From: |
Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
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To: |
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References |
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REF-PT21-80-242-000 582, NUDOCS 8007210092 |
Download: ML19320D195 (4) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217H8711997-10-15015 October 1997 Part 21 Rept Re Potential Safety Hazard for Some 3/4 Sch 40 Pipe Shipped to CP&L & VA Power Corp.Matl Has Been Found to Have Areas Where Wall Thickness Falls Below Minimum Allowed by SA 312 Specification.Customers Have Been Notified ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected 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 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 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 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 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 ML20044G5431993-05-26026 May 1993 Part 21 Rept Re Rosemount Model 1154 Series H Pressure Transmitters W/Temp Performance Characteristics Not in Compliance W/Specs.Vendor in Process of Notifying Customers.Sample Notification Ltr to Util Encl ML20126F8081992-12-22022 December 1992 Part 21 Rept Re Possible Condition of Gag Plug in Cap of Valves That Cause Valves Not to Lift to Requirement for Providing Full Capacity.Affected Customers Notified.Removal of Caps &/Or Gag Plugs Recommended 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 ML20101L9661992-07-0101 July 1992 Part 21 Rept Re Discovery of Klockner-Moeller 480-volt Breaker in Tripped Condition Due to Fracture of Plastic Arm within Breaker.Two of Three Failed Breakers Sent to Mfg for Analysis.Results Expected by End of Jul 1992 ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced 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 ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets 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 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys 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 ML20153F4151988-08-12012 August 1988 Part 21 Rept Re Procurement of Heat Tracing Matls from Nelson Electric Corp Not Meeting 10CFR21 Requirements. Initially Reported on 880810.Nelson Electric Corp Removed from Approved safety-related Vendor List ML20235U0271987-10-0707 October 1987 Part 21 Rept Re Westinghouse Plant Steam Generator Tubes Susceptible to High Cycle Fatigue Failure Similar to 870715 Event at North Anna Unit 1.Caused by Mean Stress in Tube & Superimposed Alternating Stress ML20207T8061987-02-20020 February 1987 Part 21 & Deficiency Rept Re Defect in Recirculation Spray Hxs.Initially Reported on 870218.Original HX Design Did Not Consider External Pressurization of Diaphragm Seal Plate W/O Presence of Internal Pressure as Balance.Mods Scheduled ML20211E1661987-01-28028 January 1987 Part 21 & Deficiency Rept Re Rockwell Engineering Co Steel Columns W/Laminations in Web.Initially Reported on 861112. Ultrasonic Testing of Suspect Matls Completed.Action Plan to Replace 13 Defective Columns Summarized ML20214H7521986-11-12012 November 1986 Part 21 Rept Re Potential Defect in New Svc Water Spray Array Support Sys Mfg by Inland Steel Co.Initially Reported on 861107.Positive Identification & Ultrasonic Testing of Suspect Matls Will Be Completed by 861201 ML20214F9771986-11-0707 November 1986 Part 21 Rept Re New Svc Water Spray Array Sys Supports Supplied by Inland Steel Co.Util Will Provide Positive Identification & Ultrasonic Testing Results of Suspect Matl. Identification Process Will Be Complete by 861201 ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms 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 ML20197J6371986-05-12012 May 1986 Part 21 Rept Re Possibility of Power Supply hang-up When Energizing Slv Relays.Changes Made in Power Supply Circuitry.Slv Relays,W/Mods Incorporated in Latest Designs, Extensively Tested W/O Power Supply Failures ML20137X3891986-02-27027 February 1986 Part 21 Rept Re Possible Defect in Model KMG-HRH Noble Gas Radiation Monitor W/Enhanced Detector Model KDGM-HR. Initially Reported on 860222.Vendor Will Request Utils for Listed Plants to Determine If Monitors Defective ML20137S4441985-11-26026 November 1985 Part 21 Rept Re Unparallel Fitup of Nut to Mating Surface of Connecting Rod Cap & Nonperpendicular Faces of Nuts to Thread Pitch Line.Nuts & Bolts in Assembled Calvert Cliffs Onsite Spare Engine Will Be Replaced ML20133B2511985-09-16016 September 1985 Part 21 Rept Re Defective Electronically Coded Vinyl Key Cards,Pyrotronics Model 1310,used for Security Electronic Access Control Sys.Initially Reported on 850913.Five Defective Cards Destroyed.New Cards Will Be Tested ML20125B1611985-06-0606 June 1985 Supplemental Part 21 Rept Re Addl Circuit Breakers,Furnished as Spares,W/Overcurrent Trip Devices That May Have Short Time Delay Band Lever.Items Require Insp & Replacement If Link Found Incorrect ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended RBG-18701, Attachment of Final Deficiency Rept DR-138 Re ITE-Gould Type 2150 Overload Relays Out of Calibr.Relays Sent Back & Replaced w/L10 Overload Relays.Response to Request for Addl Info Re Surry & North Anna SPDS Encl1984-08-20020 August 1984 Attachment of Final Deficiency Rept DR-138 Re ITE-Gould Type 2150 Overload Relays Out of Calibr.Relays Sent Back & Replaced w/L10 Overload Relays.Response to Request for Addl Info Re Surry & North Anna SPDS Encl ML20094D9061984-07-19019 July 1984 Interim Deficiency Rept,Item 176 Re Kerite Co Single Conductor Power Cables Damaged,But Undetected by Insp & Testing.Initially Reported on 840619.Final Rept by 841215 ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified ML20088A6231984-03-28028 March 1984 Part 21 Rept Re Abnormal Wear on Linear Converter Units Mfg & Furnished to Power Generating Facilities.Caused by Actuator Hunting.All Customers Provided Field Lubrication Procedure ML20081C5111984-03-0909 March 1984 Part 21 Rept Re Status Update Concerning Abnormal Wear on Linear Converters.Test Program Underway.Results of Investigation Indicate Excessive Wear Caused by Hunting of Control Circuitry ML20087P7951984-03-0808 March 1984 Interim Part 21 Rept Re Linear Converters Furnished by Pacific Air Products.Initially Reported on 840213.Vendor Investigation of Possible Causes of Excessive Wear Underway. Next Rept by 840730 ML20086L0921984-01-30030 January 1984 Part 21 Rept Re Linear Converter Device W/Possible Generic Defect.Initially Reported on 840116.Written Notifications Issued.Customer Responses Should Be Received by 840331.Final Rept Will Be Submitted by 840430 ML20086L0981984-01-17017 January 1984 Part 21 Rept Re Linear Converter Device W/Possible Generic Defect.Initially Reported on 840116.Preliminary Analysis Indicates Excessive Wear of Brass Shaft Guides.Next Rept Will Be Submitted within 90 Days.Supporting Info Encl ML20086N0421984-01-0202 January 1984 Final Part 21 Rept Re Potential Problem Concerning Radiography of Branch Connection Welds Covered by Reinforcing Pads.Welds at Byron,Braidwood & North Anna Acceptable.Weld 7 at Clinton Reradiographed PLA-1902, Interim Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Also Reportable Per Part 21.Initially Reported on 830912. Permanent Design Mod Will Be Implemented.Final Rept Will Be Submitted in Dec 19831983-10-10010 October 1983 Interim Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Also Reportable Per Part 21.Initially Reported on 830912. Permanent Design Mod Will Be Implemented.Final Rept Will Be Submitted in Dec 1983 ML20086N2381983-10-0404 October 1983 Supplemental Part 21 Rept Re Radiographic Record Evaluation, Supplying Addl Data to 830624 Submittal.Records Show That 90 Degree Branch Connections Furnished to North Anna 1 & 2 Jobsites.No Nozzles Supplied to Zimmer.Related Info Encl PLA-1872, Second Interim Deficiency Rept Re GE Reactor Mode Switch. Initially Reported on 830407.Mode Switch Redesigned.Sample Will Be Independently Tested.Also Reported Per Part 21.Final Rept Will Be Submitted by Dec 19831983-09-30030 September 1983 Second Interim Deficiency Rept Re GE Reactor Mode Switch. Initially Reported on 830407.Mode Switch Redesigned.Sample Will Be Independently Tested.Also Reported Per Part 21.Final Rept Will Be Submitted by Dec 1983 ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl 1997-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su 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. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with 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. ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable 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 ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,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 ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr 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 ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr 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 ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power 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 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 ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. 1999-09-08
[Table view] |
Text
ATTAGED IS A PART 21 REPORT FROM IE PAIL UNIT - ROOM 359 E/W
,.PART21IDEfEIFICATIONNO.. 3o - 2 M2-o o a C0FPANY NATE pid
'DATE OF LETTER. 7/st/f d DOCKET NO. So-3 A r j ro - 3 3 r DATE DISTRIBUTED V //o ORIGINAL REPORTg SUPPlDENTARY 3
DISTRIBUTION:
~
REACTOR (R)
[ FUEL CYCE & SAFEGUARDS (S)
IEFILES [MTERIALS (M) IE FILES AD/ROI(2) IEFILES AD/SG AD/RCI-(2) AD/FFMSI AD/RDI REGIONS I,ILIII,IV,V REGIONSI,II,III,IV,V PEGIONS I,II,III,IV,V VENDOR BR. R-IV VENDOR BR. R-IV VENDOR BR. R-IV L0EB / IPA FfB c15 NFES / FCFE SS-395 NRP/ DOL AEOD FfB 7602 L0EB/FPA FIB 5715 NIES / SG SS-881 NRR/ DOE AEOD FIB 7602 L0EB/ffA FIB 5715 NRR/DSI CENTRALFILES 016 AEOD FTB 7602
~ NRP/ DST CENTRAL FILES ( GRON) CENTPAL FILES 016 NRR/ DOL PDR CEEPAL FILES (CHRON)
CBERAL FILES 016 lPDR CENFPAL FILES SS-396 CENTRAL FILES (CHRON) TERA PDR PDR .
IPDR IPDR TERA N
ACTION:
PRELIMINARY EVALUATION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLOWUP AS SHOWN BELOW:
lE
$ NRR ffES _
OTHER l SG THIS DOCUMENT CONTAINS FFMSI POOR QUAUTY PAGES p q180 0N REV:7/9/80 1
VinorNIA Enzcrarc 4.Nn POWER COMPANY Hrenxoxo,VzmoxxzA 20262 July 2, 1980 A9b TO - }bi -00 6 Mr.-Janes P. O'Reilly, Director Serial No. SS2 Office of Inspection and Enforcement N0/FHT:bau U. S. Nuclear Regulatory Cornission Dochet Nos: 50-3.38 Region II 50-339 101 Marietta Street, Suite 3100 50-280 Atlanta, Georgia 30303 50-281 License Nos: NPF-4
. 7 DPR-32 DPR-37
Dear Mr. O'Reilly:
On June 27, 1980, a report was made under the provisions of 10CTR21 con-corning the existence of a non-conservative assu=ption in the cold shutdown desiga basis boron dilution accident analysis in the North Anna FSAR.
In accordance with the reporting requirenents -of 10CFR21, tae following information is subnitted:
A. Nane and address of reporting individual:
Mr. E. A. Baun, Executive Manager
-I.icensing and Quality Assurance P. O. Box 26666 Richnond, Virginia 23261 E. ' Facility, activity and/or conponent affected:
North Anna Power Station Units 1 and 2 Boron Dilution Accident Analyses C.
Nanc or ...- mstructing' the facility or supplying the cooponent, activity or service:
I?estinghouse Electric Corporation, NSSS vendor D.
~
-. Description of defect, deficiency.'or failure to comply:
During a review of the FSAR safety analyses for boron dilution accidents, it was deterrined that a non-conservative.assunption was made for the reactor coolant system volume during cold shut-down conditions. The use of an incorrect systen volume yields non-conservative results.
Mr. James P. O'Reilly 2
- Uestinghouse has been perferning a general review of the safety significance of inadvertent boron dilution at shutdcun conditions, and has identified the following concerns:
- 1. .Therc ccy be insufficient indication of an inadvertent dilution event so as to assure timely action by the operator prior to a return to critical.
- 2. Without positive operator. acticn, the potential existe for system overpressurization and limited fuel dananc.
I:. Date of' determination of reportability:
' June 27,1980 F. Sinilar couponents, activities, or services:
While the above accident analysis is outside the license design basis for Surry Units 1 and 2, they are also reviewing for susceptibility to inadvertent boron dilution.
G. Corrective action which has been, is being, or vill be taken, the individual responsible and the length of time to coeplete the action:
We have initiated a review of inadvertent boron dilutions for cold or hot shutdown conditions for North Anna Units ' and 2 and Surry Units 1.and 2. A review vill be perforced to icentify and analyze additional boron dilution accidents that may be applicable to these units.
Until the results of our review are available, and pending the results of a generic safety review now being perforced by 1.'estinghouse,
.the following interin actions will be implenented inmediately:
- 1. During shutdown coaditions and while on the residual heat removal system, a minimum of two shutdown banks vill be available for trip (fully withdrawn) whenever dilution /boration capability exists.
- 2. Following either source range high flux at shutdown alarn or trip of the withdrawn bank, the operator vill terminate the dilution and intiate boration immediately.
- 3. 11e source range detectors and high flux at shutdown alarm vill be verified es . operable during shutdown.
II . Other information: ,
-None.
_ _j t o-
!!r. i Jaren F. O'Reilly 3 If you have any: questions or: require additional infor-ation, please
.-contact:this office.
Very truly yours, OrfginaT Sfgned Ey P. , n . 7n ~ n E. R. Sylvia
? tanager-Fuclear Operations and l'aintenance cc: Director,- Office of Insp.>ction and '
. Enforcement (3) .
U. S. Nuclear Regulatory Comr.ission
'4ashington, D. _ C. 20555 e-a Y
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