ML20085D422
From kanterella
Jump to navigation
Jump to search
| ML20085D422 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/24/1972 |
| From: | Bessac N CAROLINA POWER & LIGHT CO. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20085D421 | List: |
| References | |
| NUDOCS 8307250654 | |
| Download: ML20085D422 (1) | |
Similar Documents at Robinson | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20247E0701989-07-20020 July 1989
[Table view]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 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 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 ML20203P0981986-04-25025 April 1986 Special Rept:On 860329,mechanical Fire Penetration Returned to Svc After Being Inoperable for Greater than 7 Days.Caused by Unacceptable Repair on 860327.Foam Sealant Equipment Repaired & Personnel Trained ML20154R0261986-03-13013 March 1986 Special Rept:On 860204,motor-driven Fire Pump Taken Out of Svc to Permit Divers to Enter Circulating Water Intake Structure.Intake Bay Dewatered on 860206 to Perform Addl Insps & Maint.Intake Bay Flooded on 860211.Part 21 Related ML20128C2161985-04-16016 April 1985 Special Rept:On 850318,RCS Iodine Radioactivity Spike Occurred.Cause Not Stated.Subsequent Sampling Met Requirements of Tech Spec 3.1.4.RCS I-131 Dose Equivalent Returned to Previously Experienced Levels on 850320 ML20093M0131984-10-0505 October 1984 Special Rept:As Result of Extensive Util Fire Barrier Penetration Insp Program,Number of Deficient Fire Barrier Penetrations Discovered.Penetrations Will Be Upgraded/ Dispositioned Prior to Startup ML20081C9881984-03-0606 March 1984 Special Rept:On 840131,six Hose Stations,Seven non-Tech Spec Hose Stations & Two Hydrants Inoperable Due to Isolation of Water Loop for Bldg Const.Addl Support for Rerouted Fire Water Piping Provided ML20082H6531983-11-23023 November 1983 Ro:On 831103,plant Shutdown for Steam Generator Tube Insp. Results Listed.Outage Still in Progress.Final Insp Results Forthcoming in 14-day LER ML20081M0991983-11-0909 November 1983 RO 82-009:specific Procedures to Test Motor Operated Valve Torque Switch Settings Not in Place by 830930.Caused by Committing Resources to Other Recent Regulatory Requirements.Procedures Will Be Established ML20080P7031983-09-29029 September 1983 Ro:On 830928,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20078D4291983-09-27027 September 1983 Ro:On 830926,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Cooler Declared Inoperable.Repairs Initiated. Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20080M0281983-09-19019 September 1983 Ro:On 830916,Tech Spec Instantaneous Release Limit for Radioiodine Exceeded.Investigation Continuing ML20081F8571983-09-12012 September 1983 Ro:On 830905,facility Shut Down Due to Secondary Leak in Steam Generator A.Two Tubes Exhibited through-wall Indications Which Should Have Been Plugged.Tubes Plugged & Tested Satisfactorily ML20076H7021983-08-24024 August 1983 Ro:On 830823,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Svc Water to Cooler Isolated.Repairs Performed ML20081F8821983-07-0505 July 1983 Ro:On 830704,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Operability Testing of Containment Spray Pumps Completed.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20151H7281983-04-28028 April 1983 Ro:On 830427,svc Water Pump a Removed from Svc for Normal Preventative Maint & Replaced W/Rebuilt Spare Pump. Post-maint Testing Resulted in Pump Over Current Trip.Caused by Internal Binding of Rebuilt Pump ML20073R2761983-04-25025 April 1983 Ro:On 830424,svc Water Booster Pump B Declared Inoperable Due to Bearing Failure & Plant Shutdown Commenced Following Pump a Trip Due to Blown Control Power Fuses.Fuses Replaced & Pump a Restarted.Investigation Continuing ML20073H9381983-04-11011 April 1983 Ro:On 830410,svc Water Leak Discovered on Containment Fan Cooler HVH-3.Svc Water Immediately Isolated.Condition Reportable Per IE Bulletin 80-24 as Degradation of Containment Boundary ML20072E1681983-02-28028 February 1983 RO-82-009 Re Failure of Motor Operated Valve RHR-759A. Due to Larger than Anticipated Work Scope,Completion Date for Corrective Actions Revised.Insp & Testing of Torque Switch Will Be Completed by End of Next Refueling Outage ML20063M1101982-08-31031 August 1982 Ro:On 820811,RHR Containment Suction Valve RHR-861A Found Opening Only Halfway & Promptly Declared Inoperable. Requests Extended 48-h Maint on Valve.Valve Not Completely Disassembled & Total Scope of Repair Not Established ML20063M1411982-08-0303 August 1982 Ro:On 820731,during Hot Shutdown,Leak Observed Coming from Control Rod Drive Mechanism Valve for Rod L-11.Leak Identified as Abnormal Degradation of RCPB ML20063M1141982-07-16016 July 1982 Ro:On 820715,small Leak in Form of Mist Found on Hydrogen Vent Header 2 Motor Cooler.Header Secured & Svc Water Isolated.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20054H4561982-06-18018 June 1982 Ro:On 820428,PT-9.13 Revealed Failure in Power Supply to Damper Relay Panel B1 (Train B) Concurrent W/Failed Relay for Zone 10 (South Cable Vault) on Panel A1 (Train A). Correction in Progress & Completion Expected by 821231 ML20063M1051982-04-27027 April 1982 Ro:On 820426,during Refueling outage,100% Eddy Current Insp of All Steam Generators Revealed Pluggable Indications of 4.4% & 1.5% on Generators B & C,Respectively.Generators Classified as Sampling Category C-3 ML20063M3131982-04-21021 April 1982 Ro:On 820416,routine Reading of Contractor Health Physics Technician TLD Indicated 6.6 Rem.Cause Not Stated.Backup Dosimetry Did Not Confirm Reading.Investigation Results to Be Submitted ML20084S8631978-01-30030 January 1978 Ro:On 780129,RCS Pressure Exceeded Tech Spec Limit by 60 Psig.Cause Not Stated.Rhr Pumps Restarted to Reduce Pressure ML20084S8831977-08-26026 August 1977 Ro:On 770825,Westinghouse Notified Util of Probable Error in Calculation of Sodium Hydroxide Concentration in Containment Spray Additive Tank.Caused by Procedural Error. Concentration Increased & New Analysis Initiated ML20084S8901977-08-15015 August 1977 Telecopy Ro:On 770812,Westinghouse Informed Util of Incorrect Tech Spec Limits of Pressurizer Heatup & Cooldown Limits.Tech Spec States Heatup & Cooldown Rates Shall Not Exceed 200 F & New Limits Equal 300 F ML20084S9041977-06-0707 June 1977 Telecopy Ro:On 770607,charging Pump High Speed Alarm Received & Pressurizer Level Decreased.Charging Pump C from Svc for Venting,Pump B Failed to Maintain Normal Pressurizer Level & Pump a Being Repaired ML20084S9211977-01-26026 January 1977 Telecopy Ro:On 770125,flow Paths from Boric Acid Tanks Made Inoperable for Valve Repair ML20086D2601976-12-0101 December 1976 RO:761117,discovered Canopy Seal Welds for Two Control Rod Drive Mechanism Housings Had Small Pin Hole Leaks BSEP-76-1374, Ro:On 761119,RHR Low Pressure Coolant Injection Valves E11-FO15A & B Had Marginal Breaker Magnetic Trip Settings. Cause Appears to Be Generic.Breakers Being Replaced1976-11-19019 November 1976 Ro:On 761119,RHR Low Pressure Coolant Injection Valves E11-FO15A & B Had Marginal Breaker Magnetic Trip Settings. Cause Appears to Be Generic.Breakers Being Replaced ML20086F4061976-11-17017 November 1976 Rept of Incidents/Occurrences for 760102-1117 BSEP-76-1143, Ro:On 760922,engineering Analysis Delineated Potential Problem W/Primary Containment Instruments 2-CAC-AT-1259 & 2-CAC-AT-1263.Dehumidifiers May Trip in Event of Loca.Caused by Excessive Heat.Short Sensing Lines Isolated1976-09-23023 September 1976 Ro:On 760922,engineering Analysis Delineated Potential Problem W/Primary Containment Instruments 2-CAC-AT-1259 & 2-CAC-AT-1263.Dehumidifiers May Trip in Event of Loca.Caused by Excessive Heat.Short Sensing Lines Isolated ML20086D3391976-08-18018 August 1976 Ro:On 760817,while Performance PT 22 on Auxiliary Feedwater sys,V2-16A Would Not Open Electrically from Rtgb.Redundant Equipment Operated Satisfactorily,Proving Ability to Feed Steam Generator in Emergency Conditions ML20086D3621976-08-0606 August 1976 Ro:On 760806,util Notified by Westinghouse of Recent Developments Re Westinghouse Safety Analyses.Limiting Values for Fq & Pnh Reduced to 2.27 & 1.49,pending Further Investigation ML20086D4021976-04-0202 April 1976 Ro:On 760402,discovered That Boric Acid Heat Tracing Circuit 56 Had No Current Flow & Was Inoperative.Breaker Opened in Each Heat Trace Power Panels ML20086D4121976-03-15015 March 1976 Ro:On 760312,util Notified by Westinghouse of Possible Error in LOCA Analysis.Error Involves Oversight of Potential Effect of Steam Generator Tube Plugging.Limiting Valve of Fq Reduced to 2.26 Pending Further Investigation ML20085D0361973-08-0909 August 1973 Ro:Water Vol in Safety Injection Accumulators Found Below Min Required Tech Spec Limit.Caused by Incorrectly Fixed High & Low Level Alarm Setpoints.New Setpoint Documentation Approved ML20085D1121973-06-27027 June 1973 Ro:On 730620,during Test on Turbine Redundant Overspeed Trip Sys,Turbine Trip Inadvertently Initiated.Caused by Turbine Stop Valve Limit Switch Failure.Switch Adjusted ML20085D2321973-04-26026 April 1973 Ro:On 730327,individual Received Overexposure to Radiation While Checking for Leakage in Reactor Sump Area.Technicians Instructed on Importance of Knowing Exposure Limit & Remaining Dose of Individual Working in Area ML20085D2241973-04-24024 April 1973 Ro:On 730410,spill of Water from Refueling Water Storage Tank to Plant Storm Drainage Sys Occurred.Caused by Leakage in Line Between Spent Fuel Cooling Sys & Safety Injection Sys Due to High Pressure.Piping & Valves Pressurized ML20085D3171973-02-0909 February 1973 Ro:On 721220,leak Detected Inside Containment Vessel in Joint Where Auxiliary Feedwater Pipe B,4-FW-23 Joins Main Feedwater Pipe B,16-FW-10.Caused by Saddle Welds Not Designed as Pressure Boundary.Boundary Rewelded ML20085D2631972-11-30030 November 1972 Ro:On 721105,power Operated Relief Valve RV-2 on Steam Line B Failed to Close.Caused by Relief Valve Sticking in Open Position.Inner Valve & Guide Bushing Polished ML20085D3991972-11-10010 November 1972 Ro:On 721019,boric Acid Tank B & Boron Injection Tank Found Low in Boron Concentration.Caused by Improper Seating of Suction & Discharge Isolation Valves of Tank.Tank Recirculated W/Boric Acid Tank a ML20085D4071972-10-20020 October 1972 Telecopy Ro:On 721019,boron Injection Tank & Boric Acid Tank B Found to Have Low Concentration of Boric Acid.Steps Initiated to Return Tanks to Normal Concentration ML20085D3731972-09-11011 September 1972 Ro:On 720726 Following Part Length Rod Control Sys Alarm, Frequency Sensor Relay Found Inoperable.Relay Replaced ML20085D4221972-07-24024 July 1972 Ro:On 720716,concentration of Boron Injection Tank Found Diluted Below Tech Spec Limit.Caused by Plugged Recirculation Path Between Boric Acid & Injection Tanks. Temporary Hose Rigged to Recirculate Acid Between Two Tanks ML20085D1371972-07-18018 July 1972 Ro:On 720709,steam Line Isolation Valve B Malfunctioned During Periodic Test.Caused by Sheared Pin in Linkage Between Valve Stem & Disc.Valve Repaired 1989-07-20 Category:TEXT-SAFETY REPORT MONTHYEARML20217A1691999-09-22022 September 1999
[Table view]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 |
Text
- - - - - - - - - -
7 o O f
. Carolina Power & Light Company '
.p?rf,,
.? -
Raleigh, North Carolina 27602 [f. <p July 24, 1972 'O/dyg
.a w, ~(;
Cx4, ..
n fsi"'
Mr. John F. O' Leary, Director 50-261 Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C. 50545 H. B. ROBINSON PLANT LICENSE DPR-23 BORON INJECTION TANK DILUTION
Dear Mr. O' Leary:
In accordance with paragraph 6.6.1.a, Technical Specifications, it is reported that on July 16, 1972, while operating at power, the con-centration in the Boron Injection Tank was found to be diluted below the specified concentration. The normal recirculation path between the Boric Acid Tanks and the Boron Injection Tank was determined to be plugged with sclidified boric acid. A temporary hose was rigged to recirculate boric acid between the Boric Acid Tanks and the Boron Injection Tank and the concentration in the Beron Injection Tank returned to normal. Repairs were simultaneously initiated to remove the solidified boric acid. All repairs have been completed, the system tested for correct operation, the temporary hose remove 1, and the system returned to normal operation.
The incident was discussed with representatives of the Directorate of Regulatory Operations, Atlanta, Georgia and these discussions confirmed by a telegram on July 16, 1972.
Yours very truly, c
N. B. essac Manager Nuclear Generation NBB:me -(775) cc: Mr. C. D. Barham Mr. B. J. Furr Mr. E. E. Utley [
0307250654 721221 PDR ADOCK 05000261 S PDR i
- - - - - - 4AC3
Retrieved from "https://kanterella.com/w/index.php?title=ML20085D422&oldid=2740195"