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 Isolated
From kanterella
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| ML20084S926 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/23/1976 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| BSEP-76-1143, NUDOCS 8306200092 | |
| Download: ML20084S926 (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 |
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O I Brunswick Steam Electric Plant P.O. Box 458
[ Southport, NC 28461 September 23, 1976 E FILE: B3516 SERIAL: BSEP/76-1143 E-g Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Region II, Suite 818 g 230 Peachtree Street, N.W.
- Atlanta, Georgia 30303
Dear Mr. Moseley:
On September 22, 1976, we received an engineering analysis from our engineering department in Raleigh which delineated a potential problem with our Primary Containment 02 /H2 instruments (2-CAC-AT-1259 L 2-CAC-AT-1263) . The analysis pointed out that in the event of a LOCA the dehumidifiers at the instruments may trip out because of excessive heat of approximately 170*F from certain short length sensing lines from the containment structure. A dehumidifier tripout renders the instrument inoperabic. The short sensing lines have been isolated and tagged out. (3 lines for 2-CAC-AT-1259 & 2 lines for 2-CAC-AT-1263),
j This constitutes a reportable occurrence as defined in Technical Specification 6.11.2.a(9) and was reported to Mr. H. A. Wilber of your office on September 22, 1976.
?
, Very truly yours, A
r C/ ,,b W B.J. Furr, Manager Brunswick S.E. Plant
. RSS/dla cc: H.R. Banks i
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