Methods to Prevent Boron Precipation in Long-Term Following Postulated Loca.ML19322B616 |
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Oconee |
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12/18/1975 |
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DUKE POWER CO. |
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ML19322B615 |
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NUDOCS 7912040642 |
Download: ML19322B616 (9) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20151T2571985-12-20020 December 1985 Mechanical Maint Technical Rept, Unit 3 Containment Bldg Tendon Surveillance, Jul 1977 - Jul 1980 ML20135G5891985-09-0303 September 1985 Rev 0 to B&W Owners Group Emergency Operating Procedures Technical Bases Document. W/Three Oversize Drawings ML20151K2671984-03-31031 March 1984 Final Rept:Failure Modes & Effects Analysis of Integrated Control Sys/Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Vol 1 - Main Rept & Vol 2 - App a ML20151K2491984-03-29029 March 1984 Draft Oconee-1 AC Electrical Distribution Control & Protection Design Features ML20151K2761983-10-28028 October 1983 Failure Modes & Effects Analysis for Oconee 1 Nuclear Power Station Makeup & Purification Sys ML20080E0101983-10-0303 October 1983 Failure Modes & Effects Analysis for Oconee 1 Nuclear Power Station Makeup & Purification Sys, Preliminary Draft ML20080E6061983-08-26026 August 1983 Failure Modes & Effects Analysis of Integrated Control Sys/ Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Interim Rept ML20072B7961983-02-15015 February 1983 Control Room Review Plan for Oconee,Mcguire & Catawba Nuclear Stations,Duke Power Co ML20117J3641983-01-31031 January 1983 Evaluation of Oconee Nuclear Station,Duke Power Co ML20117J3571981-07-31031 July 1981 Evaluation of Oconee Nuclear Power Station ML19323A1621980-03-26026 March 1980 TMI-Plus One:Toward a Safer Nuclear Power Program. ML19249D8631979-09-30030 September 1979 Description of Proposed Mod to Radiological Effluent Treatment Facility, Preliminary Rept.Oversize Drawings Encl ML19308A7471979-09-27027 September 1979 Jocassee Development Rept on 790825 Earthquake & Effects on Jocassee Structures. ML19322B8741979-08-24024 August 1979 Addl Info to 790824 Response to IE Bulletin 79-05C Nuclear Incident at TMI Including Supplemental Small Break Analysis ML19312C1281979-08-16016 August 1979 Mgt & Technical Resources:Experience & Qualifications of Steam Production Dept General Office Staff. ML19312C7981979-07-30030 July 1979 Response to IE Bulletin 79-05C, Nuclear Incident at Tmi. ML19259C4821979-05-0909 May 1979 Effect of Closing Oconee Nuclear Plants on Ability to Meet Summer Peak Demands. ML19312C5841978-07-14014 July 1978 Proposed Mod of Hpis. ML19316A1201978-07-14014 July 1978 Rept on Seismic Activity at Lake Jocassee,780301-0531. ML19316A1351978-04-0404 April 1978 Rept on Seismic Activity at Lake Jocassee,771201-780228 ML19319A7261978-03-0101 March 1978 Info & Evaluation Re Fracture Toughness of Steam Generator & Reactor Coolant Pumps Support Matls. ML19354C2851978-02-28028 February 1978 Possible Geologic/Seismicity Relationships in Vicinity of Facility from Available Data & Repts. Oversize Maps Encl ML19354C2861978-01-19019 January 1978 Rept on Preliminary Investigation of Seismicity Near Lake Keowee,Oconee County,SC,771230-780115. ML19317E6991978-01-16016 January 1978 Fire Protection Program Comparison to NRC Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls & Qa. ML19316A1231977-11-30030 November 1977 Rept on Seismic Activity at Lake Jocassee,770901-1130. Oversize Earthquake Charts Encl ML19317E7261977-10-14014 October 1977 Fuel Assembly 1D40. ML19312C5811977-09-24024 September 1977 Generator Tube Leak Status Rept. ML19316A1301977-09-0202 September 1977 Jocassee Dam Northwestern Sc:Estimate of Existing Strain & Cracking Potential from Hypothetical Foundation Displacements. ML19319A7301977-08-31031 August 1977 Safety Assessment of Steam Generator Tube Leakage. ML19316A1361977-08-31031 August 1977 Rept on Seismic Activity at Lake Jocassee,770601-0831. Oversize Map Encl ML19316A1291977-08-26026 August 1977 Steam Generator Tube Leak Status Rept. ML19308A8381977-07-18018 July 1977 Requalification Program for NRC Licensed Personnel, 731211.Revised on 740703,750107,0221,760930 & 770718 ML19316A3121977-04-21021 April 1977 Evaluation of Potential for Turbine Bldg Flooding. ML19312C3611977-03-30030 March 1977 Qualification of Power Distribution Connector for Use in 15kV Rated Medium Voltage Electrical Penetrations. ML19312C1251977-03-22022 March 1977 Rept on Seismic Activity at Lake Jocassee Between 760601 & 770228. ML19316A1131976-12-31031 December 1976 Response to App a to Branch Technical Position Apcsb 9.5.1, Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to 760710. ML19317D7041976-10-14014 October 1976 Evaluation of Potential Reactor Vessel Overpressurization. ML19308B2771976-10-0101 October 1976 Engineering Geology of Keowee-Toxaway Project. ML19260C1781976-09-30030 September 1976 Jocassee Hydro-Station Seismic Studies Summary Rept. Cover Ltr & Oversize Drawings Encl ML19312C1591976-08-0606 August 1976 Evaluation of Post-LOCA Boric Acid Concentration Control Sys for Facility Reactors. ML19340A1241976-04-16016 April 1976 Criticality Evaluation for Dry Storage of Fresh Fuel Assemblies in Oconee Unit 3 Spent Fuel Pool. ML19316A1171976-04-13013 April 1976 Attachment A:Structural Analysis of Worn Surveillance Specimen Holder Tubes. ML19340A1571976-04-12012 April 1976 Surveillance Holder Tube Rept. ML19322B6161975-12-18018 December 1975 Methods to Prevent Boron Precipation in Long-Term Following Postulated Loca. ML19322B6121975-11-14014 November 1975 Reactor Vessel Support Evaluation for LOCA Loadings. ML19312C8231975-08-12012 August 1975 Safety Evaluation Supporting Util Application to Amend License DPR-55 for Mod of Spent Fuel Storage Facility ML19317E5061975-08-0101 August 1975 Partial Loop ECCS Analysis. 1998-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 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 ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20247L9041997-12-31031 December 1997 1997 Annual Rept for Duke Energy Corporation & Saluda River Electric Cooperative,Inc,Financial Statements as of Dec 1997 & 1996 Together W/Auditors Rept ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20134N7121997-02-20020 February 1997 Safety Evaluation Accepting Relief Request 96-04 for Plant ML20138L2151997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 ML20138L2281996-12-31031 December 1996 Revised Monthly Operating Repts for Dec 1996 for Oconee Nuclear Station,Units 1,2 & 3 ML20133C1231996-12-23023 December 1996 Informs Commission of Staff Review of Request for License Amends from DPC to Perform Emergency Power Engineered Safeguards Functional Test on Three Oconee Nuclear Units ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20086M0851995-06-29029 June 1995 DPC TR QA Program ML20077R3631994-12-31031 December 1994 Monthly Operating Repts for Dec 1994 for Bfnpp ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20064L2001994-01-31031 January 1994 Final Rept EPRI TR-103591, Burnup Verification Measurements on Spent-Fuel Assemblies at Oconee Nuclear Station ML20062K7481993-12-0101 December 1993 ISI Rept for Unit 2 McGuire 1993 Refueling Outage 8 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20046C1291993-08-0202 August 1993 LER 93-007-00:on 930701,determined That Unit 1 Ssf Rc Makeup Sys Inoperable in Past Due to Design Deficiency.Operations Procedures Revised to Reflect Newly Calculated Operating Limits for Rc Makeup Pump,Rcps & RCS.W/930802 Ltr ML20056G0131993-07-27027 July 1993 Rev 0 to ISI Rept Unit 2 Oconee 1993 Refueling Outage 13 ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20097G0421992-05-31031 May 1992 Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML19332D5391989-10-31031 October 1989 Core Thermal-Hydraulic Methodology Using VIPRE-01. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20239A6991987-11-30030 November 1987 Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum) ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20236Q9491987-10-31031 October 1987 Monthly Operating Repts for Oct 1987 ML20235W9611987-09-30030 September 1987 Monthly Operating Repts for Sept 1987 ML20234B1861987-08-31031 August 1987 Monthly Operating Repts for Aug 1987 ML20237K4761987-07-31031 July 1987 Monthly Operating Repts for Jul 1987 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20235S6311987-06-30030 June 1987 Monthly Operating Repts for June 1987 1999-01-05
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l 1 METHODS TO PREVENT BORON PRECIPITATION IN THE LONG-TERM l, FOLLOWING A POSTULATED LOSS OF COOLANT ACCIDENT
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1 METHODS TO PREVENT BORON PRECIPITATION IN THE LONG-TERM l FOLLOWING A POSTULATED LOSS OF COOLANT ACCIDENT l In Duke Power Company's April 16, 1975 submittal, it was demonstrated that if a core circulation in excess of 40 gpm following a postulated loss-of-coolant accident was maintained, the resulting boron concentration buildup would be limited to a C/Co of less than 11. This concentration buildup assures that boron precipitation does not adversely affect long term cooling capability.
In order to assure that this minimum 40 gpm core circulation can be maintained, a station modification will be made to each Oconee unit to provide a gravity flowpath from the hot leg nozzle to the Reactor Building sump through the decay heat drop line. A 2" ID, or larger, drain line with two electric motor operated isolation valves (LP-X and LP-Y) will be installed on the decay heat drop line above valve LP-1 (See attached figures.). This line will allow drainage of highly concentrated water from the top of the core for all postulated loss-of-coolant accidents, allowing dilute water to enter the core and thus promote significant core circulation. The gravity head in these lines will assure that a flow in excess of 40 gpm will exist following the postulated LOCA.
The above described drain line is not single failure proof in itself; therefore, an additional flowpath is necessary. For Unit 1, another 2" ID, or larger, drain line and electric motor operated valve (LP-Z) will be installed below valves LP-1 and LP-2. This will establish a second flowpath from the hot leg to the Reactor Building sump through the decay heat drop line and will enable the single failure criteria to be met.
For Units 2 and 3, the existing flowpath through valves LP-1, LP-2, LP-3, LP-4 (Unit 2 only) to the A LPI pump suction or to the Reactor Building sump through valve LP-19 provides an alternate gravity flowpath.
The following additional information concerning the design and required changes in procedures is provided:
(a) The gravity flowpaths for the proposed mode of boron dilution are identified in the attached PO drawings.
(b) The elevation of the 36" ID outlet nozzle is 809' 6". For Unit 1, the decay heat line begins at the bottom of the hot leg nozzle, elevation 808', and continues downward to valves LP-1 and LP-2 at elevation 798' 6",
the line then turns upward and penetrates the Reactor Building at elevation 812'. The tap for valves LP-X and LP-Y will be above LP-1, and the tap for LP-Z will be below LP-2 before the decay heat line turns upward. The sizing and location of the drain lines will be such that a minimum flow of 40 gpm, following a postulated LOCA, will be assured.
For Units 2 and 3, the decay heat line begins at the bottom of the hot leg nozzle, elevation 808', and continues downward to valves LP-1 and l-