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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML17354A4801997-04-24024 April 1997 Special Rept:On 970401,Overpressure Mitigating Sys High Pressure Alert Annunciated at 400 Psig During Discussion Between Nuclear Plant Supervisor & Reactor Control Operator. Pressure Control Was Reduced & Individuals Were Counseled ML17353A5391996-01-19019 January 1996 Ro:On 951221 & 29 3B EDG Failed Due to Loose Fitting on Fuel Oil Priming Pump Suction Line & Loose Fitting on Discharge Line.Leaking Fittings Tightened & All Fittings on Fuel Oil Suction Lines Verified Tight ML17353A5331996-01-12012 January 1996 Special Rept:On 951215,4A EDG Failure Occurred.Caused by Faulty Voltage Regulator.Voltage Regulator Replaced ML17352B0351995-02-20020 February 1995 Special Rept:On 950201,rapid Start of EDG Attempted & Alarms Failed to Sound When EDG Did Not Start.Caused by High Resistance on Contacts of Relay.Relay Replaced & EDG Retested satisfactorily.W/950220 Ltr ML17352A7421994-07-28028 July 1994 Special Rept:On 940702,3A Emergency Diesel Generator Failed.Caused by Failure of Speed Switch Module.Module Replaced ML17352A0781993-06-24024 June 1993 Special Rept:On 930610,SJAE SPING-4 Monitor RAD-3-6417 Out of Svc for More than Seven Days Due to Failed Detector. Temporary Moisture Separator Being Installed,In Area of Lower Ambient Temp Which Is Expected to Reduce Moisture ML17349A9061993-06-10010 June 1993 Special Rept:On 930525,nonsafety-grade Standby Feedwater Pumps Isolated for 18 H & 15 Minutes to Establish Boundary to Repair Valve 4-20-130.Standby Feedwater Sys Supply Returned to svc.Marked-up Administrative Procedure Encl ML17349A7591993-03-10010 March 1993 Special Rept:On 930225,4B EDG Failed.Caused by Intermittent Connection,Resulting in Voltage Spikes.Cold Solder Joint Repaired & EDG Voltage Regulator Cabinet Inspected ML17349A6791993-02-16016 February 1993 Special Rept:On 930116,actuation of Overpressure Mitigating Sys Occurred Due to Increase in RCS Pressure.Caused by Delay in Stopping Charging Pump During Pressurizer Bubble Collapse.Procedures Revised & Evaluation Performed ML17349A5591992-12-18018 December 1992 Special Rept:On 921127,PORV PCV-3-456 Opened Due to High Pressure in Rcs.Initial Temps of Shell Side Water in SG Found to Be Approx 145 F.Caused by Lack of Pressure Absorbing Bubble in Pressurizer.Procedure Revised ML17349A5341992-12-0404 December 1992 Special Rept:On 921106 & 12,20th Yr Tendon Insp Determined That lift-off Value for Hoop Tendon 13H54 & Dome Tendon 1D40 Below Min Design Prestress Force.Tendons Restored to Required Level.Addl Rept to Be Submitted by 930129 ML17349A4361992-10-19019 October 1992 Special Rept:On 920918,overpressure Mitigating Sys Actuation Occurred Due to Increase in RCS Pressure Experienced as motor-operated Valves Approached Fully Closed Position. Night Order Issued & Inservice Testing Procedure Revised ML17349A3821992-09-0707 September 1992 Special Rept:On 920824,Hurricane Andrew Struck Plant W/Both Units in Mode 4.Sample Line from Plant Vent Stack to SPING-4 Severed.Caused by Extreme Weather Due to Hurricane.Plant Change/Mod 92-104 Issued to Repair Sample Line ML17349A3221992-08-0505 August 1992 Special Rept:On 920706,hoop Tendon Group Found to Have Measured Normalized lift-off Force Below Predicted Lower Limit.Cause Under investigation.Lift-off Forces in Tendons 42H31,42H32 & 42H33 Restored to Required Level ML17349A3051992-07-10010 July 1992 Special Rept:Three Surveillance Tendons,Inspected on 920612, 19 & 29 Found W/Measured Normalized lift-off Force Below Predicted Lower limit.Lift-off Forces Restored to Required Level of Integrity.Addl Rept Will Be Sent by 920915 ML17348A8211991-01-14014 January 1991 Special Rept:From 901206 to 21,listed Fire Barriers,Doors, Detector Alarms,Manholes & Water Tanks Not Returned to Functional Status within 7 Days.Compensatory Measures Implemented ML17348A7831990-12-18018 December 1990 Special Rept:On 901109,13,27,29 & 30,non-functional Fire Barrier Penetration Not Returned to Functional Status within Seven Days.Caused by Damaged Door & Damaged Thermolag. Compensatory Measures Implemented ML17348A7481990-11-15015 November 1990 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments ML17348A6151990-10-19019 October 1990 Special Rept Re Listed Fire Barrier Penetrations Not Returned to Functional Status within 7 Days ML17348A5451990-08-29029 August 1990 Corrected Rev 1 to Special Rept:On 900527,discovered That nonsafety-related Standby Feedwater Pumps Unavailable for Plant.Caused by Failure of Valve Stem Bushing Resulting from Overstress of Bushing.Replacement Bushing Mfg Onsite ML17348A5391990-08-29029 August 1990 Rev 1 to Special Rept:On 900527,discovered That Both nonsafety-related Standby Feedwater Pumps Unavailable for Facility.Caused by Failure of Valve Stem Bushing.Replacement Bushing Mfg on Site ML17348A5111990-08-16016 August 1990 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments,Per Tech Spec 6.9.3.c.Fire Protection Impairments Issued for Support of Backfit Const Work.Util Continues to Implement Compensatory Measures ML17348A4261990-07-17017 July 1990 Special Rept:On 900604 & 13,fire Barriers Breached for More than 7 Days.Caused by Welding in Area.Plant Continues to Implement Compensatory Measures as Applicable ML17348A3281990-06-20020 June 1990 Special Rept:Notifies NRC of Fire Protection Sys Impairments Opened Since Last Rept Which Have Been Open for Longer than 7 Days & Those Previously Not Reported Closed,Per Tech Spec 3.14.5.b.Plant Continues to Implement Compensatory Measures ML17348A3341990-06-19019 June 1990 Special Rept:On 900527,discovered That Both nonsafety-related Standby Feedwater Pumps Unavailable. Condition Discovered While Aligning Pumps to Steam Generators.Cause Unknown.Replacement Bushing Mfg Onsite ML17348A2571990-05-18018 May 1990 Special Rept:Fire Barriers & Other Fire Protection Sys Inoperable for Greater than 7 Days,Thus,Violating Tech Spec 3.14.5.b.Plant Continues to Implement Compensatory Measures as Applicable ML17348A2011990-04-17017 April 1990 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments.Fire Protection Impairments 3306 Issued for Repair of Fireproofing Impaired by Removal of Conduits.Compensatory Measures Still Underway ML17347B6301990-03-20020 March 1990 Special Rept:From 900131-0303,listed Fire Barriers, Penetrations,Doors & Detector Alarms Opened for More than 7 Days.Compensatory Actions Implemented,As Applicable ML17347B5841990-02-20020 February 1990 Special Rept:On 900102,04,19,25 & 29,fire Barriers, Penetrations & Diesel Fire Pump P-101 Breached & Not Returned to Operable Status within 7 Days.Compensatory Measures Continue to Be Implemented ML17347B5221990-01-12012 January 1990 Special Rept:On 891129,30,1202,05,07,08,11,13 & 14,listed Fire Barriers,Doors & Penetrations Opened Longer than Tech Spec Limits.Compensatory Measures Implemented,As Applicable ML17347B4931989-12-19019 December 1989 Special Rept:Listed Fire Barriers,Doors & Penetrations Breached for More than 7 Days.Barrier 106-F Closed When Hole Discovered While Removing Electrical Cable.Compensatory Measures Implemented ML17347B4201989-11-16016 November 1989 Special Rept:Provides List of Nonfunctional Fire Barrier Penetration Not Returned to Functional Status within 7 Days, Per Tech Spec 3.14.5.b.Caused by Performance of Fire Protection Surveillance.Compensatory Measures Implemented ML17347B4011989-10-30030 October 1989 Special Rept:Breached Fire Barriers & Other Fire Protection Sys Impairments Existing for More than 7 Days.Cause Not Stated.Fire Protection Impairments 2820 & 2821 Issued for Installation of Conduits ML17347B3781989-10-13013 October 1989 Special Rept Providing List of Nonfunctional Fire Barrier Penetrations Not Returned to Function Status within 7 Days. Plant Continues to Implement Compensatory Measures as Applicable ML17347B3361989-09-14014 September 1989 Special Rept Informing of non-functional Fire Barrier Penetration Not Returned to Functional Status within 7 Days. Fire Protection Impairments Issued for Access to Areas of Const Work.Compensatory Measures Implemented ML17347B2691989-08-16016 August 1989 Special Rept:On 890706-21,breached Fire Barriers & Other Fire Protection Sys Impairments Open Longer than Tech Spec Limits ML17347B2591989-08-14014 August 1989 Special Rept:On 881203,spent Fuel Pit Exhaust high-range Noble Gas Monitor Inoperable for Greater than 7 Days.Caused by Extensive Nature of Calibr Performed & Repairs to Sample Sys Piping.Monitor Returned to Operable Status on 890318 ML17347B2441989-08-0707 August 1989 Special Rept:On 890613-30,breached Fire Barriers & Other Fire Protection Sys Impairments Not Returned to Functional Status within 7 Days,Per Tech Spec 3.14.5.b.Impairments Being Evaluated & Work on Corrections in Progress ML17347B1611989-07-0303 July 1989 Special Rept:On 890505,0607 & 08,fire Barriers Breached & Other Fire Protection Sys Impairments Occurred.Fire Protection Impairment 2477 on Alarm Point Taken Out of Svc for Welding in Fire Zone 054.Work Ongoing ML17345A7631989-06-20020 June 1989 Special Rept Re Plant Vent Stack Exhaust High Range Noble Gas Effluent Monitor Inoperable for More than 7 Days.Caused by Inability of Monitor to Perform Intended Function in Event of Max Hypothetical Accident.Shielding Installed ML17345A7161989-05-31031 May 1989 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments.Fire Protection Impairment 2458, Opened 890420,to Repair Penetration Seal,Still Being Worked. Plant Continues to Implement Compensatory Measures ML17345A6381989-04-21021 April 1989 Special Rept:On 890322,condenser Air Ejector High Range Noble Gas Monitor Removed from Svc in Order to Performed Maint & Became Inoperable for Greater than 7 Days.Monitor Scheduled to Be Returned to Svc Prior to Restart of Unit ML17345A6391989-04-21021 April 1989 Special Rept:On 890312,16 & 27 Fire Protection Impairments Opened for Repairs & Not Returned to Functional Status within 7 Days,Per Tech Spec 3.14.5.b.Discrepancies Identified by Fire Door Surveillance Being Evaluated ML17347B0791989-04-0404 April 1989 Special Rept:On 890228,0302,04 & 07,listed Fire Protection Impairments Opened & Not Returned to Functional Status within 7 Days.Plant Continues to Implement Compensatory Measures as Applicable ML17347B0341989-03-23023 March 1989 Special Rept:Nonfunctional Fire Barrier Penetration Not Returned to Functional Status within 7 Days.Caused by Plant Mods.Detector Operability Verified & Fire Watch Patrols Established ML17347A9821989-03-0101 March 1989 Special Rept:On 890130,main Steam Line Radiation Monitor Inoperable for Greater than 7 Days.Caused by Inability to Obtain Proper Response from Cs-137 Stick Source & Kr-85 Check Source During Replacement of Damaged Cable & Detector ML17347A9581989-02-0707 February 1989 Special Rept:On 890104,Fire Protection Impairment (Fpi) 2227 Issued for Holes Through Fire Barrier 75F.Caused by Implementation of Plant Mod.Detector Operability Verified & Fire Patrol Established.Fpi 1926 Closed on 890103 ML17345A6311989-01-0909 January 1989 Special Rept:Listed Fire Protection Sys Impairments Opened. Causes Include Leaching in Thermolag Insulation,Grout Void & Faulty Latching & Locking Mechanisms on Fire Doors.List of Impairments Open in Excess of Tech Spec Limits Encl ML17345A6011988-12-16016 December 1988 Special Rept:Notifies of Three Fire Protection Impairments Incurred in Excess of Tech Spec Permitted Time Limits.On 881114,fire Protection Impairment 2125 Issued for Breach of Penetration 054-H001 to Provide Access to Repair Hanger ML17345A5381988-11-18018 November 1988 Special Rept:On 881012,13,25 & 28,five Fire Protection Impairments Left Open in Excess of Tech Specs Permitted Time Limits.Caused by Either Plant Mods or Equipment Maint.Plant Continues to Implement Compensatory Measures as Applicable 1997-04-24
[Table view] Category:LER)
MONTHYEARML17354A4801997-04-24024 April 1997 Special Rept:On 970401,Overpressure Mitigating Sys High Pressure Alert Annunciated at 400 Psig During Discussion Between Nuclear Plant Supervisor & Reactor Control Operator. Pressure Control Was Reduced & Individuals Were Counseled ML17353A5391996-01-19019 January 1996 Ro:On 951221 & 29 3B EDG Failed Due to Loose Fitting on Fuel Oil Priming Pump Suction Line & Loose Fitting on Discharge Line.Leaking Fittings Tightened & All Fittings on Fuel Oil Suction Lines Verified Tight ML17353A5331996-01-12012 January 1996 Special Rept:On 951215,4A EDG Failure Occurred.Caused by Faulty Voltage Regulator.Voltage Regulator Replaced ML17352B0351995-02-20020 February 1995 Special Rept:On 950201,rapid Start of EDG Attempted & Alarms Failed to Sound When EDG Did Not Start.Caused by High Resistance on Contacts of Relay.Relay Replaced & EDG Retested satisfactorily.W/950220 Ltr ML17352A7421994-07-28028 July 1994 Special Rept:On 940702,3A Emergency Diesel Generator Failed.Caused by Failure of Speed Switch Module.Module Replaced ML17352A0781993-06-24024 June 1993 Special Rept:On 930610,SJAE SPING-4 Monitor RAD-3-6417 Out of Svc for More than Seven Days Due to Failed Detector. Temporary Moisture Separator Being Installed,In Area of Lower Ambient Temp Which Is Expected to Reduce Moisture ML17349A9061993-06-10010 June 1993 Special Rept:On 930525,nonsafety-grade Standby Feedwater Pumps Isolated for 18 H & 15 Minutes to Establish Boundary to Repair Valve 4-20-130.Standby Feedwater Sys Supply Returned to svc.Marked-up Administrative Procedure Encl ML17349A7591993-03-10010 March 1993 Special Rept:On 930225,4B EDG Failed.Caused by Intermittent Connection,Resulting in Voltage Spikes.Cold Solder Joint Repaired & EDG Voltage Regulator Cabinet Inspected ML17349A6791993-02-16016 February 1993 Special Rept:On 930116,actuation of Overpressure Mitigating Sys Occurred Due to Increase in RCS Pressure.Caused by Delay in Stopping Charging Pump During Pressurizer Bubble Collapse.Procedures Revised & Evaluation Performed ML17349A5591992-12-18018 December 1992 Special Rept:On 921127,PORV PCV-3-456 Opened Due to High Pressure in Rcs.Initial Temps of Shell Side Water in SG Found to Be Approx 145 F.Caused by Lack of Pressure Absorbing Bubble in Pressurizer.Procedure Revised ML17349A5341992-12-0404 December 1992 Special Rept:On 921106 & 12,20th Yr Tendon Insp Determined That lift-off Value for Hoop Tendon 13H54 & Dome Tendon 1D40 Below Min Design Prestress Force.Tendons Restored to Required Level.Addl Rept to Be Submitted by 930129 ML17349A4361992-10-19019 October 1992 Special Rept:On 920918,overpressure Mitigating Sys Actuation Occurred Due to Increase in RCS Pressure Experienced as motor-operated Valves Approached Fully Closed Position. Night Order Issued & Inservice Testing Procedure Revised ML17349A3821992-09-0707 September 1992 Special Rept:On 920824,Hurricane Andrew Struck Plant W/Both Units in Mode 4.Sample Line from Plant Vent Stack to SPING-4 Severed.Caused by Extreme Weather Due to Hurricane.Plant Change/Mod 92-104 Issued to Repair Sample Line ML17349A3221992-08-0505 August 1992 Special Rept:On 920706,hoop Tendon Group Found to Have Measured Normalized lift-off Force Below Predicted Lower Limit.Cause Under investigation.Lift-off Forces in Tendons 42H31,42H32 & 42H33 Restored to Required Level ML17349A3051992-07-10010 July 1992 Special Rept:Three Surveillance Tendons,Inspected on 920612, 19 & 29 Found W/Measured Normalized lift-off Force Below Predicted Lower limit.Lift-off Forces Restored to Required Level of Integrity.Addl Rept Will Be Sent by 920915 ML17348A8211991-01-14014 January 1991 Special Rept:From 901206 to 21,listed Fire Barriers,Doors, Detector Alarms,Manholes & Water Tanks Not Returned to Functional Status within 7 Days.Compensatory Measures Implemented ML17348A7831990-12-18018 December 1990 Special Rept:On 901109,13,27,29 & 30,non-functional Fire Barrier Penetration Not Returned to Functional Status within Seven Days.Caused by Damaged Door & Damaged Thermolag. Compensatory Measures Implemented ML17348A7481990-11-15015 November 1990 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments ML17348A6151990-10-19019 October 1990 Special Rept Re Listed Fire Barrier Penetrations Not Returned to Functional Status within 7 Days ML17348A5451990-08-29029 August 1990 Corrected Rev 1 to Special Rept:On 900527,discovered That nonsafety-related Standby Feedwater Pumps Unavailable for Plant.Caused by Failure of Valve Stem Bushing Resulting from Overstress of Bushing.Replacement Bushing Mfg Onsite ML17348A5391990-08-29029 August 1990 Rev 1 to Special Rept:On 900527,discovered That Both nonsafety-related Standby Feedwater Pumps Unavailable for Facility.Caused by Failure of Valve Stem Bushing.Replacement Bushing Mfg on Site ML17348A5111990-08-16016 August 1990 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments,Per Tech Spec 6.9.3.c.Fire Protection Impairments Issued for Support of Backfit Const Work.Util Continues to Implement Compensatory Measures ML17348A4261990-07-17017 July 1990 Special Rept:On 900604 & 13,fire Barriers Breached for More than 7 Days.Caused by Welding in Area.Plant Continues to Implement Compensatory Measures as Applicable ML17348A3281990-06-20020 June 1990 Special Rept:Notifies NRC of Fire Protection Sys Impairments Opened Since Last Rept Which Have Been Open for Longer than 7 Days & Those Previously Not Reported Closed,Per Tech Spec 3.14.5.b.Plant Continues to Implement Compensatory Measures ML17348A3341990-06-19019 June 1990 Special Rept:On 900527,discovered That Both nonsafety-related Standby Feedwater Pumps Unavailable. Condition Discovered While Aligning Pumps to Steam Generators.Cause Unknown.Replacement Bushing Mfg Onsite ML17348A2571990-05-18018 May 1990 Special Rept:Fire Barriers & Other Fire Protection Sys Inoperable for Greater than 7 Days,Thus,Violating Tech Spec 3.14.5.b.Plant Continues to Implement Compensatory Measures as Applicable ML17348A2011990-04-17017 April 1990 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments.Fire Protection Impairments 3306 Issued for Repair of Fireproofing Impaired by Removal of Conduits.Compensatory Measures Still Underway ML17347B6301990-03-20020 March 1990 Special Rept:From 900131-0303,listed Fire Barriers, Penetrations,Doors & Detector Alarms Opened for More than 7 Days.Compensatory Actions Implemented,As Applicable ML17347B5841990-02-20020 February 1990 Special Rept:On 900102,04,19,25 & 29,fire Barriers, Penetrations & Diesel Fire Pump P-101 Breached & Not Returned to Operable Status within 7 Days.Compensatory Measures Continue to Be Implemented ML17347B5221990-01-12012 January 1990 Special Rept:On 891129,30,1202,05,07,08,11,13 & 14,listed Fire Barriers,Doors & Penetrations Opened Longer than Tech Spec Limits.Compensatory Measures Implemented,As Applicable ML17347B4931989-12-19019 December 1989 Special Rept:Listed Fire Barriers,Doors & Penetrations Breached for More than 7 Days.Barrier 106-F Closed When Hole Discovered While Removing Electrical Cable.Compensatory Measures Implemented ML17347B4201989-11-16016 November 1989 Special Rept:Provides List of Nonfunctional Fire Barrier Penetration Not Returned to Functional Status within 7 Days, Per Tech Spec 3.14.5.b.Caused by Performance of Fire Protection Surveillance.Compensatory Measures Implemented ML17347B4011989-10-30030 October 1989 Special Rept:Breached Fire Barriers & Other Fire Protection Sys Impairments Existing for More than 7 Days.Cause Not Stated.Fire Protection Impairments 2820 & 2821 Issued for Installation of Conduits ML17347B3781989-10-13013 October 1989 Special Rept Providing List of Nonfunctional Fire Barrier Penetrations Not Returned to Function Status within 7 Days. Plant Continues to Implement Compensatory Measures as Applicable ML17347B3361989-09-14014 September 1989 Special Rept Informing of non-functional Fire Barrier Penetration Not Returned to Functional Status within 7 Days. Fire Protection Impairments Issued for Access to Areas of Const Work.Compensatory Measures Implemented ML17347B2691989-08-16016 August 1989 Special Rept:On 890706-21,breached Fire Barriers & Other Fire Protection Sys Impairments Open Longer than Tech Spec Limits ML17347B2591989-08-14014 August 1989 Special Rept:On 881203,spent Fuel Pit Exhaust high-range Noble Gas Monitor Inoperable for Greater than 7 Days.Caused by Extensive Nature of Calibr Performed & Repairs to Sample Sys Piping.Monitor Returned to Operable Status on 890318 ML17347B2441989-08-0707 August 1989 Special Rept:On 890613-30,breached Fire Barriers & Other Fire Protection Sys Impairments Not Returned to Functional Status within 7 Days,Per Tech Spec 3.14.5.b.Impairments Being Evaluated & Work on Corrections in Progress ML17347B1611989-07-0303 July 1989 Special Rept:On 890505,0607 & 08,fire Barriers Breached & Other Fire Protection Sys Impairments Occurred.Fire Protection Impairment 2477 on Alarm Point Taken Out of Svc for Welding in Fire Zone 054.Work Ongoing ML17345A7631989-06-20020 June 1989 Special Rept Re Plant Vent Stack Exhaust High Range Noble Gas Effluent Monitor Inoperable for More than 7 Days.Caused by Inability of Monitor to Perform Intended Function in Event of Max Hypothetical Accident.Shielding Installed ML17345A7161989-05-31031 May 1989 Special Rept Re Breached Fire Barriers & Other Fire Protection Sys Impairments.Fire Protection Impairment 2458, Opened 890420,to Repair Penetration Seal,Still Being Worked. Plant Continues to Implement Compensatory Measures ML17345A6381989-04-21021 April 1989 Special Rept:On 890322,condenser Air Ejector High Range Noble Gas Monitor Removed from Svc in Order to Performed Maint & Became Inoperable for Greater than 7 Days.Monitor Scheduled to Be Returned to Svc Prior to Restart of Unit ML17345A6391989-04-21021 April 1989 Special Rept:On 890312,16 & 27 Fire Protection Impairments Opened for Repairs & Not Returned to Functional Status within 7 Days,Per Tech Spec 3.14.5.b.Discrepancies Identified by Fire Door Surveillance Being Evaluated ML17347B0791989-04-0404 April 1989 Special Rept:On 890228,0302,04 & 07,listed Fire Protection Impairments Opened & Not Returned to Functional Status within 7 Days.Plant Continues to Implement Compensatory Measures as Applicable ML17347B0341989-03-23023 March 1989 Special Rept:Nonfunctional Fire Barrier Penetration Not Returned to Functional Status within 7 Days.Caused by Plant Mods.Detector Operability Verified & Fire Watch Patrols Established ML17347A9821989-03-0101 March 1989 Special Rept:On 890130,main Steam Line Radiation Monitor Inoperable for Greater than 7 Days.Caused by Inability to Obtain Proper Response from Cs-137 Stick Source & Kr-85 Check Source During Replacement of Damaged Cable & Detector ML17347A9581989-02-0707 February 1989 Special Rept:On 890104,Fire Protection Impairment (Fpi) 2227 Issued for Holes Through Fire Barrier 75F.Caused by Implementation of Plant Mod.Detector Operability Verified & Fire Patrol Established.Fpi 1926 Closed on 890103 ML17345A6311989-01-0909 January 1989 Special Rept:Listed Fire Protection Sys Impairments Opened. Causes Include Leaching in Thermolag Insulation,Grout Void & Faulty Latching & Locking Mechanisms on Fire Doors.List of Impairments Open in Excess of Tech Spec Limits Encl ML17345A6011988-12-16016 December 1988 Special Rept:Notifies of Three Fire Protection Impairments Incurred in Excess of Tech Spec Permitted Time Limits.On 881114,fire Protection Impairment 2125 Issued for Breach of Penetration 054-H001 to Provide Access to Repair Hanger ML17345A5381988-11-18018 November 1988 Special Rept:On 881012,13,25 & 28,five Fire Protection Impairments Left Open in Excess of Tech Specs Permitted Time Limits.Caused by Either Plant Mods or Equipment Maint.Plant Continues to Implement Compensatory Measures as Applicable 1997-04-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 Ltr ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 Ltr ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 Ltr ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 Ltr ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B1901998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 981112 Ltr ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17. ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B1311998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With 981012 Ltr ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17354B0981998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With 980915 Ltr ML17354B0771998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4.W/980810 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354B0241998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4.W/980709 Ltr ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9711998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4. W/980611 Ltr ML17354A9231998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4.W/980511 Ltr ML17354A8821998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4.W/980409 Ltr ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A8311998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Turkey Point,Units 3 & 4.W/980311 Ltr ML17354A7871998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Turkey Point,Units 3 & 4.W/980209 Ltr ML17354A7581997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Turkey Point,Unit 3 & 4.W/980112 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A7381997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Turkey Point,Units 3 & 4.W/971215 Ltr ML17354A7211997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Turkey Point,Units 3 & 4.W/971114 Ltr ML17354A7491997-10-13013 October 1997 SG Insp Rept. ML17354A8851997-10-13013 October 1997 FPL Units 3 & 4 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 960408-971013. ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6791997-10-0606 October 1997 COLR Unit 4 Cycle 17, for Turkey Point ML17354A6811997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Turkey Point,Units 3 & 4.W/971009 Ltr 1999-09-30
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~~~~~~i~a j.~u UVCUMENT DISTRIBUTION REGULA'lC INFORMATION DISTRIBUTIO~YSTEM (RIDE)
SYSTEM ACCESSION'BR:9212100117 DOC.DATE 92/12/04 NOTARIZED: NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME, AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power & Light Co.
RECIP.NAME. RECIPIENT AFFILIATION EBNETER,S.D. Region 2 (Post 820201)
SUBJECT:
Special rept:on 921106 & 12,20th yr tendon insp determined
,that lift-off value for hoop tendon 13H54 & dome tendon lD40 below min design prestress force. Tendons restored to required level.Addi rept to be submitted by .930129.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
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0 ~t P.O. Bo 9100, Miami, FL. 33102-9100 FPL OEi; 04 ~>S~
L-92-330 10 CFR 50.36 Stewart D. Ebneter Regional'dministrator U. S. Nuclear Regulatory Commission 101. Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323
Dear Mr. Ebneter:
Re: Turkey Point Unit 4 Docket No. 50-251 Special Report Twentieth Year Tendon Inspection Low Lift-Off Force In accordance with Florida Power and Light Company, (FPL) Turkey Point Units 3 and 4 Technical Specification 3.6.1.6 a., the enclosed Special Report is provided. This report summarizes the low lift-off force inspection results for hoop tendon 13H54 and dome tendon 1D40.
As discussed with the staff on November 30, 1992, a second hoop tendon 35H38 measured a lift-off value below the minimum design prestress force and in accordance with Technical Specification 3.6.1..6 a.,
tendon 35H38'ill be addressed in a separate Special Report to be submitted to the .NRC by December 1'8, 1992.
An additional report will be transmitted to the NRC by January 29, 1993, summarizing the surveillance testing of all hoop and dome tendons inspected during the Unit 4 twentieth year inspection.
Should there be. any questions, please contact us.
Very truly yours, Qj P/~AN.. ,Gd.
T. F. Plunkett Vice President Turkey Point Nuclear TFP/RJT/rt Enclosure cc: USNRC, Document Control Desk, Washington, D.C.
Senior Resident Inspector, USNRC, Turkey Point Plant 1000OJ 92i2100ii7 921204 PDR ADOCK 0500025i pre f:
S, PDR an FPL Group company
il 0 Enclosure NRC S ecial Re ort Turkey Point Unit 4 Twentieth Year Tendon Inspection Low Lift-Off Force on Hoop Tendons 13H54 and Dome Tendon 1D40
0 L-92-330 Special Report Page .2 of 7 TABLE OF CONTENTS 1.0 PURPOSE/SCOPE 2'. 0 ENGZNEERZNG EVALUATZON.
3.0 CONCLUSZON 4.0 CORRECTZVE ACTZONS
5.0 REFERENCES
'l L-92-330 Special Report Page 3 of 7 1.0 Pu ose Sco e During the performance of the twentieth year tendon surveillance of the Turkey Point Unit 4 containment post-tensioning system, two surveillance tendons, 13H54 (inspected on November 6, 1992) of the hoop tendon group and 1D40 (inspected on November 12, 1992) of the dome tendon group were found to have a measured normalized lift-off force below the predicted lower limit (References 5.4 and 5.5) .
Consequently, in accordance with the requirements of the Turkey Point Plant Technical Specifications 4.6.1.6.1 (a), additional lift-off measurements on the adjacent tendons (13H53 and 13H55, inspected on November 6, 1992 and 1D38 and 1D41 inspected on November 13, 1992) were taken for each of the applicable surveillance tendons. Zn each case, since the measured normalized lift-off force in at least one of these adjacent tendons was between the predicted lower limit and 90%
of the predicted lower limit, Turkey Point Unit 4 entered a 15 day ACTZON statement to the LZMZTZNG CONDZTZON OF OPERATZON (Technical Specification 3 '.1.6) . This ACTZON statement required restoration of the tendon(s) to the required level of integrity within 15 days and performance of an engineering evaluation of the cont'ainment, and the submittal of a Special Report to the NRC within 30 days.
The evaluation of the structural integrity of the containment post-tensioning system is included in this engineering evaluation.
2.0 En ineerin Evaluation The Turkey Point Unit 4 containment is a post-tensioned, reinforced concrete structure comprised of a vertical cylinder with a shallow dome and suppozted on a conventional reinforced concrete foundation base slab. The vertical cylinder wall is provided with a system of vertical and hoop tendons. Vertical tendons are anchored at the top surface of the ring girder and at the bottom of the base slab. Each hoop tendon is anchored at alternate vertical buttresses nominally 120 degrees apart. Tendons in the dome consist of three groups of tendons oriented at 120 degrees with respect to each other and are anchored at the vertical face of the dome zing girder.
The tendon surveillance program for the Turkey Point Nuclear Plant Unit 4 containment structure post-tensioning system has been performed at one, three and five years after the containment Znitial Structural Zntegrity Test (ZSZT), and every five years thereafter. Three dome, five hoop, and four vertical tendons were selected for the twentieth year tendon surveillance on a random basis, excluding those tendons which were previously inspected for earlier surveillances. The Turkey, Point Unit 4 twentieth year tendon surveillance is performed in accordance with the requirements of References 5.6 and 5.9 ~
A wire has been removed foz inspection from dome tendon 1D40. Zn addition, grease samples have been removed for each surveillance tendon inspected to date. The visual inspection of the tendon wire and sheath filler samples have revealed no abnormal wire corrosion or grease discoloration.
't L-92-330 Special Report Page 4 of 7.
Also, the concrete at the tendon anchorage area adjacent to the bearing plates, for all hoop tendons has been inspected. This inspection has revealed that no cracks were found which exceed the acceptance. width of 0.01 inches noted in reference 5.8, Section ZWL-3221 '(d) ~
For tendons 1D40 and 1D41, the bearing plates are located in the vicinity of a horizontal construction joint located at approximately mid-height of the ring girder. Some concrete spalling/cavities were observed at this horizontal construction joint during the Unit 3 third year tendon surveillance. The spalling was inspected and evaluated in reference 5.11, which concluded that the structural integrity of the containment is not affected. While inspecting the concrete surface in the vicinity of the bearing plates for tendons 1D40 and 1D41 during the Unit 4 twentieth year surveillance, a similar spalling/cavity was observed at this joints The subject areas were inspected, and it was concluded that the spalling observed, during the Unit 4 twentieth year
.surveillance is similar,to the condition evaluated in reference 5.11 and there will be no adverse effects on, the containment structural The appropriate corrective actions will be specified in integrity. -final the Unit 4 surveillance report to repair the spalled areas to mitigate any potential corrosion, path to the main reinforcing, steel.
The following are the predicted lower limit (PLL) and the minimum design prestress force at the anchorage for hoop and dome tendons:
Twentieth Year Predicted Lower Limit 6.63 kips/wire for Hoop and Dome Tendons.
(Reference 5.6)
Minimum Design Prestress Force 6.29 kips/wire (Based on Original Anchorage for Hoop Tendons Design)'t (Reference 5.3)
Minimum Design Prestress Force ~ 6.55 kips/wire (Based on Original Design) at Anchorage for Dome Tendons (Reference 5.3)
The lift-off forces which are below the surveillance tendons predicted lower limit occurred (13H54) and its adjacent in one of the hoop tendons (13H53 and 13H55) and in one of the dome surveillance tendons
,(1D40) and one of its adjacent tendons (1D41).
From references 5.4 and 5.5, the results of the surveillance on, hoop and dome tendons are as follows:
Measured Normalized Percentage Tendon Lift-Off Force ki s wire of PLL 13H53 6.27 94.6%
13H54 6.37 96.1%
13H55 6.26 94.4%
Average 6.30 kips/wire 95.0%
L-92-330 Special Report Page 5 of 7 Measured Normalized Percentage Tendon Lift-Off Force ki s wire of PLL 1D38 6.84 103.2%
1D40 6.54 98.6%
1D41 6.29 94.9%
Average 6.56 kips/wire 98.9%
As shown, the average lift-offprestress force for the hoop, tendon group is force (6 29 kips/wire) .
larger than the minimum design Also, the average lift-off force for ~
the dome tendon group is larger force (6.55 kips/wire) than the minimum design prestress . Therefore, it is concluded that the subject tendon groups presently provide adequate prestress force to maintain the containment integrity. This conclusion is consistent with the guidance provided in Section 7.1.5 of Regulatory Guide 1.35 (Reference 5.7) and Section IWL-3221.1 (a) of ASME Code (Reference 5.8).
The magnitude of the Unit 4 low lift-off forces for the subject hoop and dome tendons is similar to the Unit 3 lift-off force measurements and correlates well with the results of the evaluation provided to the NRC by Letter L-92-262, dated September 14, 1992 (Reference 5.10) for the Unit 3 low lift-off values. Therefore, it can be stated that the probable cause of the Unit 4 low lift-offmeasurements is also due to increased. tendon wire steel relaxation losses resulting from the temperatures experienced by the tendons. The lift-off readings for the remaining surveillance tendons will provide additional data to further investigate the extent of this condition. Upon completion os the lift-off testing, an engineering evaluation will be prepared to include the additional data and the results of the investigation relative to this condition. A more detailed report will be submitted to the NRC following completion of the tendon surveillance.
2.1 Review Of Re ulator Guides and ASME Code Section XI Acce tance Criteria Regulatory Guide 1.35 (reference 5.7), Section 7.0, and ASME Code Section XI (reference 5 '), Section IWL-3221.1, were reviewed relative to the tendon lift-off acceptance criteria to provide additional justification for the adequacy of the containment post-tensioning system. The following summarizes this review:
a) Section 7.1.5 of reference 5.7 and Section IWL-3221.1 (a) of reference 5.8 require that the average of all measured tendon forces be equal to or greater than the minimum required prestress force at the anchorage.
b) Section 7 '.2 of reference 5.7 implies that, lift-off force for a surveillance if the measured tendon lies above 95% of the predicted lower limit, no additional lift-off testing of adjacent tendons is required and the condition should be considered acceptable.
I
il 0 L-92-330 Special Report Page 6 of 7 The measured normalized lift-off forces for surveillance tendons 13H54 and 1D40 were above 95% of the predicted. lower limit. This meets the requirement of reference 5.7 (Criterion (b) above), and no additional testing would have been required if this criterion had been applied.
Finally, as shown in Section 2.0, the average lift-off force for hoop tendons is 1'arger than the minimum design prestzess force (6.29 kips/wire) which satisfies criterion (a) above Also, the average lift-off force for dome tendons is larger than the minimum
~
design prestzess force (6.55 kips/wize). Therefore, based on this
.review, it can also be concluded that the Unit 4 hoop and dome tendon groups have sufficient pzestress force to maintain. the containment integrity, and the intent of the acceptance criteria included in References 5.7 and 5.8 is satisfied.
2.2 Desi' Maz ins Available in the Post-Tensionin S stem Turkey Point UFSAR (reference 5.1), Section 5.1.2 states that any three adjacent tendons in any tendon group can be lost without significantly affecting the strength of the containment structure.
This design feature considers the load redistribution capabilities of the containment shell.
3.0 Conclusion Based on the available margins existing in the design of the Turkey Point post-tensioning system and the level of prestress force available in the subject hoop and dome tendons, it is concluded that the Unit 4 hoop and dome tendon groups have sufficient prestress force to maintain the containment integrity.
As, part of the twentieth year surveillance, lift-off testing will be performed for the remaining hoop and dome surveillance tendons. These lift-off readings will .provide additional data to further investigate the extent of this condition. Upon completion of the lift-off testing, an engineering evaluation will be prepared to include the additional data and the results of the investigation relative to this condition. A more detailed report will be submitted to the NRC following completion of the tendon surveillance.
4.0 Corrective Actions According to the Turkey Point Plant Technical Specifications 3.6.1.6 (a), the lift-off forces in tendons 13H53, 13H54, 13H55, 1D40 and 1D41 have been restored to their required level of integrity by retensioning each tendon to a level equal to or above the twentieth year predicted lower limit. The following summarizes the new lift-off forces for the subject tendons:
Measured Percenta e of Tendon Avera e Lift-Off ki s Predicted Lower Limit 13H53 621.3 104.1%
13H54 619.8 103.9%
13H55 634 ' 106.3%
1D40 622.0 104.2%
1D41 619.0 103.7%
II L-92-330 Special Report Page 7 of 7
'5 ~ 0 References 5.1 Turkey Point Units 3 and 4 Updated Final Safety Analysis Report (UFSAR), Revision 10, dated July 1992, Section 5.0 5.2 Technical Specifications, Amendment 151/146, Sections 4.6.1.6.1(a) and 3.6.1.6, and Amendments 152/147 issued via NRC letter dated August 20, 1992 5.3 'Bechtel Calculation No. C-SJ539-05, "Evaluation of the Fifteenth Year Tendon Surveillance Lift-Off Forces", Revision 0
- 5. 4 Non-Conf ormance. Report N-92-0292.
5.5 Non-Conformance Report N-92-0301 5.6 Bechtel Technical Requirements Document 21701-561-CP-l, Revision 0 for Unit 4 Twentieth Year Tendon Surveillance 5.7 Regulatory Guide 1.35, "In-service Inspection of Ungrouted Tendons in Prestressed Concrete Containment", Revision 3, dated July 1990 5.8 ASME Code, 1989 Edition,Section XI Division 1, Article IWL-3000, "Acceptance Standards" 5.9 Turkey Point Plant Procedure O-SMM-51.2, "Containment Tendon Inspection", dated June 26, 1992 5.10 FPL Transmittal to the NRC, Turkey Point Unit 3 Twentieth Year Tendon Inspection Report Hoop Tendons Low Lift-Off Force, L-92-262, dated September 14, 1992 5.11 Turkey Point Nuclear Power Plant, Unit 3, "Containment Structure Ring Girder Concrete Inspection", dated February 1975
Ik I'i