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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARRA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review 05000261/LER-1983-005, Supplemental LER 83-005/01T-1:on 830424,svc Water Booster Pump B Declared Inoperable Due to Loss of Bearing Oil.Caused by Bearing Oil Slinger Positioned Near Vent Holes.Standpipes Installed on Each Vent Hole1984-06-14014 June 1984 Supplemental LER 83-005/01T-1:on 830424,svc Water Booster Pump B Declared Inoperable Due to Loss of Bearing Oil.Caused by Bearing Oil Slinger Positioned Near Vent Holes.Standpipes Installed on Each Vent Hole 05000261/LER-1980-030, Updated LER 80-030/03L-1:on 801202 & 03,charging Pumps A,B & C Discharge Line Pressure Gauge Tap Pipe Socklets Found Leaking.Caused by Sys Design Deficiencies Allowing High Vibration.Leaks Repaired & Design Modified1983-09-30030 September 1983 Updated LER 80-030/03L-1:on 801202 & 03,charging Pumps A,B & C Discharge Line Pressure Gauge Tap Pipe Socklets Found Leaking.Caused by Sys Design Deficiencies Allowing High Vibration.Leaks Repaired & Design Modified 05000261/LER-1981-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised1982-11-17017 November 1982 Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised 05000261/LER-1980-027, Updated LER 80-027/01T-1:on 801122,relay RT-9 in Reactor Protection Train a Failed to re-energize During Periodic Test of Reactor Protection Logic.Caused by Shorting of Lead Wire Connection to Coil Wires.Relay Replaced1982-10-11011 October 1982 Updated LER 80-027/01T-1:on 801122,relay RT-9 in Reactor Protection Train a Failed to re-energize During Periodic Test of Reactor Protection Logic.Caused by Shorting of Lead Wire Connection to Coil Wires.Relay Replaced 05000261/LER-1981-002, Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modifie1982-08-20020 August 1982 Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modified 05000261/LER-1976-014, Updated LER 76-014:on 760805,util Notified by NRC That Peak Clad Temp Increase Presented by Westinghouse Should Be 50 F Higher.Caused by Using Different Versions of ECCS Model. New Limit in Effect 750825.W/760917 Ltr1976-09-17017 September 1976 Updated LER 76-014:on 760805,util Notified by NRC That Peak Clad Temp Increase Presented by Westinghouse Should Be 50 F Higher.Caused by Using Different Versions of ECCS Model. New Limit in Effect 750825.W/760917 Ltr 1997-12-19
[Table view] Category:TEXT-SAFETY REPORT
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 RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review 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 ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr 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 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl 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 ML20079H1571991-09-30030 September 1991 Nonproprietary Evaluation of Revised Transfer to Cold Leg Recirculation Procedure,Hb Robinson Unit 2 ML20086T2951991-06-14014 June 1991 Rev 1 to EQ Documentation Package Eqdp 36.0, Boston Insulated Wire Cable ML20086T2861991-03-0808 March 1991 Rev 1 to EQ Documentation Package Eqdp 11.1, Dekoron Instrumentation Cables ML20086T2561991-03-0808 March 1991 Rev 1 to EQ Documentation Package 10.0, Continental Shielded Instrument Cable ML20065K6961990-10-31031 October 1990 Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies ML20065K6971990-10-31031 October 1990 Thermal Hydraulic Compatibility Analysis of Anf High Thermal Performance Fuel for Hb Robinson,Unit 2 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 ML20247E0701989-07-20020 July 1989 Info Rept:On 890717-0804,fire Penetration Seals Will Be Removed from Svc to Allow Access for Ventilation Sys Mod. Addl Fire Barrier Penetrations Will Be Made in Wall Between RHR Pump Pit & Fuel Handling Bldg,Per Tech Spec 3.14.7.2 ML20246E9111989-03-31031 March 1989 PDC-3:Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2 ML20245H0821989-01-25025 January 1989 Criticality Safety Analysis of Hb Robinson Spent Fuel Pool W/4.2% Nominal Enrichment Fuel Assemblies ML20205T0551988-10-31031 October 1988 Responses to NRC Questions on RTD Bypass Elimination Licensing Rept ML20147E2371988-02-29029 February 1988 1987 Annual Rept - Primary Coolant Iodine Spikes ML20147B1971987-12-31031 December 1987 1987 Annual Rept - Primary Safety & Relief Valve Challenges ML20236K7731987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235W3781987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238E2741987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20235H3151987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20214W3241987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20214R5101987-04-30030 April 1987 Rev 1 to Monthly Operating Rept for Apr 1987,correcting Operation Statistics & Shutdown Experience Due to Mathematical Errors ML20215L4941987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206F3561987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20210B4141987-03-31031 March 1987 Revised Monthly Operating Rept for Mar 1987 ML20205F6021987-03-23023 March 1987 Special Rept:On 870302,noble Gas Effluent Monitor for Main Steam Line B Declared Inoperable & Svc Not Returned Until 870312.Caused by Defective Detector.Detector Replaced.High Voltage for Detector Adjusted & Sys Operation Checked ML20212P3101987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 ML20214Q7891987-01-31031 January 1987 Cycle 12,SAR ML20210R6341987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20207M2451986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 L-18-120, Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi1986-12-18018 December 1986 Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi ML20215C7911986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F3121986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20215G1081986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20215F0361986-09-29029 September 1986 Special Rept:On 860902,during Cold Shutdown,Pressurizer PORV Lifted Twice to Prevent Overpressurization.Caused by Inadvertent Action by Unit Operators.Operations Personnel Counseled Re Importance of Breaker Position Indicators ML20211C0641986-09-0909 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson Spent Fuel Storage Racks (Unpoisoned,Low Density) W/4.2% Enriched 15x15 Fuel Assemblies ML20211C0491986-09-0202 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson New Fuel Storage Vault W/4.2% Enriched 15x15 Fuel Assemblies ML20212F5321986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20202G3371986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211B5601986-05-31031 May 1986 Monthly Operating Rept for May 1986 ML20197D2651986-04-30030 April 1986 Monthly Operating Rept for Apr 1986 1999-09-22
[Table view] |
LER-2081-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised |
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2612081001R00 - NRC Website |
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NRC FORM* 366 " UPDATE REPORT - PREVIOUS REPORT DATE 1/23/81" u.S. NUCLEAR REGULATORY COMMISSION (7-77 F LICENSEE EVENT REPORT 0
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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil8 lS l CLICENSEE l H lB lR l 2 l@l 0l 0l -l 0lLICENSE 14 15 0] 0l 0l 0l -l 0 l 0l@l NUMBER 25 4 l 1l 26 1l 1l 1l@l 57 CAT LICENSE TYPE JO l
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74 75 REPORT DATE 7 8 60 61 DOCK ET NUMBER EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o l 2 l l0n January 9,1981, with the unit at 100% power, it was determined that operation with l g o ,3, lthe RPI System input to the turbine runback and auto rod withdrawal defeated and power l
, o g , , [ range channel N41 input out of service is contrary to the assumptions in the safety l
, o g g analysis prepared during the fuel reload safety evaluation. Still the probability of l l
g lnot sensing a dropped rod is small since three of the power range detectors were l l o l , l [ ope rab le . 'Ihis occurrence is reportable pursuant to Technical Specifications l oig .9.2.a(6). No adverse consequences resulted from the above condition. l 80 C DE CODE SUBC E COMPONENT CODE SUBC DE S ODE
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[_qg lNjg lWl1l2l0lg 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o lA review of the H. B. Robinson Unit 2 FSAR and Fuel Reload Safety Evaluation l
, , g identified that the rod drop analysis assumes both turblae runback and auto rod l
,,y,,gwithdrawal block. A new analysis of this event concluded that operation without l
,,,3, g these protective systems is not adverse to safety. Administrative controls, which l were implemented f ollowing this event , will be revised to delete the 70% power I
m l restriction.
- 8 9 80 ST S % POWE R OTHER STATUS Dis O RY DISCOVERY DESCRIPTION OBSERVATION i s lEl@ l1l0l0l@l ' ' "
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6 SUPPLEMENTAL INFORMATION FOR LICENSEE EVENT UPDATE REPORT 81-001, REVISION 1 I. Cause Description and Analysis, On January 7,1981, the Power Range Channel N41 was taken out of service.
Previous to this, the Rod Position Indication System (RPI) input to the turbine runback system and auto rod withdrawal circuit had been defeated due to spurious rod drop indications in an effort to prevent unnecessary thermal cycles to Reactor Coolant System (RCS) components. On January 9, 1981, it was determined, by a review of the H. B. Robinson, Unit No. 2 FSAR and Fuel Reload Safety Evaluation, that both of these documents assume that turbine runback and auto rod withdrawal defeat occur follow-ing a control rod drop. These systems are actuated by any one RPI bottom signal or a rapid flux decrease on any one power range channel.
By having N41 inoperable, a few rods located in the core region nearest N41 might not be detected by the other three power range detectors if they were to drop. Based on this review, therefore, the event was identified as reportabic pursuant to Technical Specification 6.9.2.a.6.
Since an RCCA drop event did not occur during this time, no adverse consequences resulted from the above situation.
II. Corrective Action All atfected systems were immediately returned to service when it was determined that having both inputs to the turbine runback and auto rod withdrawal systems defeated may be contrary to the FSAR and fuel reload safety analysis.
III. Correct ive Action To Prevent Recurrence A review of this issue has been completed, and an analysis has been i
performed by the fuel supplier. On the basis of this analysis, it has been concluded that even without the turbine runback and automatic rod withdrawal block protection systems, H. B. Robinson, Unit No. 2 will have acceptable thermal margin with respect to a dropped rod transient.
The results of this analysis also envelope the current reduced temper-nture and power operation.
Following this event, administrative controis were implemented to ensure that both turbine runback and auto rod withdrawal block initiating circuits are not defeated at power levels greater than 70%. Based on the analysis described above, the administrative controls governing the RPI and power range nuclear instrumentation inputs to be the tudi tne runback and automatic rod withdrawal block circuits will be revised to delete the requirement to reduce power to 70%. In general, this action will be taken when instrument problems in the rod position indication system cause false rod bottom signals leading to needless turbine 1.nbacks, or when a power range NIS channel fails or is taken out of service for maintenance and/or testing. The intent of the remaining controls will be to minimize the time these inputs are blocked. Normal operation will continue to be with the runback initiating circuits in place. No further action is considered necessary.