Chapter 13 of Oconee 1,2 & 3 PSAR, Initial Tests & Operations. Includes Revisions 1-6ML19322A761 |
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Oconee ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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12/01/1966 |
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DUKE POWER CO. |
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NUDOCS 7911210785 |
Download: ML19322A761 (6) |
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Category:PRELIMINARY SAFETY ANALYSIS REPORT & AMENDMENTS (PSAR
MONTHYEARML19322A7561967-04-0101 April 1967 Suppl to Oconee 1,2 & 3 PSAR ML19322A7701966-12-0101 December 1966 App 2A of Oconee 1,2 & 3 PSAR, Subsurface & Foundations. ML19322A7691966-12-0101 December 1966 App 1A of Oconee 1,2 & 3 PSAR, Technical Qualifications. ML19322A7721966-12-0101 December 1966 App 5A of Oconee 1,2 & 3 PSAR, Structural Design Bases. ML19322A7751966-12-0101 December 1966 App 5E of Oconee 1,2 & 3 PSAR, Liner Plate Spec. ML19322A7781966-12-0101 December 1966 App 5F of Oconee 1,2 & 3 PSAR, Reactor Bldg Instrumentation. ML19322A7571966-12-0101 December 1966 Chapter 11 of Oconee 1,2 & 3 PSAR, Radwaste & Radiation Protection. Includes Revisions 1-6 ML19322A7581966-12-0101 December 1966 App 2B of Oconee 1,2 & 3 PSAR, Seismology & Meteorology. ML19322A7591966-12-0101 December 1966 Chapter 12 of Oconee 1,2 & 3 PSAR, Conduct of Operations. Includes Revisions 1-6 ML19322A7601966-12-0101 December 1966 App 2C of Oconee 1,2 & # PSAR, Groundwater Hydrology. ML19322A7611966-12-0101 December 1966 Chapter 13 of Oconee 1,2 & 3 PSAR, Initial Tests & Operations. Includes Revisions 1-6 ML19322A7631966-12-0101 December 1966 Chapter 14 of Oconee 1,2 & 3 PSAR, Safety Analysis. Includes Revisions 1-6 ML19322A7651966-12-0101 December 1966 App 2D of Oconee 1,2 & 3 PSAR, Field Permeability Tests. ML19322A7661966-12-0101 December 1966 Chapter 15 of Oconee 1,2 & 3 PSAR, Tech Specs. Includes Revisions 1-6 ML19322A7681966-12-0101 December 1966 App 2E of Oconee 1,2 & 3 PSAR, Geology. ML19322B5141966-12-0101 December 1966 Chapter 10 of Oconee 1,2 & 3 PSAR, Steam & Power Conversion Sys. Includes Revisions 1-6 ML19322A7711966-12-0101 December 1966 App 4A of Oconee 1,2 & 3 PSAR, Once-Through Steam Generator. ML19322A7731966-12-0101 December 1966 App 5B of Oconee 1,2 & 3 PSAR, Design Program for Reactor Bldg. ML19322A7741966-12-0101 December 1966 App 5D of Oconee 1,2 & 3 PSAR, Qc. ML19322A7761966-12-0101 December 1966 App 5C of Oconee 1,2 & 3 PSAR, Design Criteria for Reactor Bldg. ML19322A7821966-12-0101 December 1966 Chapter 3 of Oconee 1,2 & 3 PSAR, Reactor. Includes Revisions 1-6 ML19322A7841966-12-0101 December 1966 Chapter 4 of Oconee 1,2 & 3 PSAR, Rcs. Includes Revisions 1-6 ML19322A7861966-12-0101 December 1966 Chapter 5 of Oconee 1,2 & 3 PSAR, Containment Sys. Includes Revisions 1-6 ML19322A7871966-12-0101 December 1966 Chapter 1 of Oconee 1,2 & 3 PSAR, Introduction & Summary. Includes Revisions 1-6 ML19322A7881966-12-0101 December 1966 Chapter 6 of Oconee 1,2 & 3 PSAR, Engineered Safeguards. Includes Revisions 1-6 ML19322A7891966-12-0101 December 1966 Chapter 8 of Oconee 1,2 & 3 PSAR, Electrical Sys. Includes Revisions 1-6 ML19322A7901966-12-0101 December 1966 Chapter 2 of Oconee 1,2 & 3 PSAR, Site & Environ. Includes Revisions 1-6 ML19322A7911966-12-0101 December 1966 Chapter 7 of Oconee 1,2 & 3 PSAR, Instrumentation & Control. Includes Revisions 1-6 ML19322B5131966-12-0101 December 1966 Chapter 9 of Oconee 1,2 & 3 PSAR, Auxiliary & Emergency Systems. Includes Revisions 1-6 1967-04-01
[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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13 INITIAL TESTS AND OPERATION 13-1
{ 13.1 TESTS PRIOR TO REACTOR FUELING 13-1 i 13.2 INITIAL CRITICALITY 13-1
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l lO LIST OF TABLES Table g 13-1 Prefueling Test Program 13-2 13-2 Posteriticality Test Program 13-3
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13 INITIAL TESTS AND OPERATION 13.1 TESTS PRIOR TO REACTOR FUELING A comprehensive Oconee Nuclear Station field testing program will be carried out to insure that equipment and systems perform in accordance with design criteria.
The test program will begin 9 to 12 months prior to reactor fueling. As installation of individual components and systems is completed, they will be tested and evaluated. The testing program will be carried out according to detd. led predetermined testing techniques and procedures. Field analysis and more detailed office analysis of cest results will be made to' verify
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that systems and components are performing satisfactorily or to recommend necessary corrective action.
In general, the types of tests will be classified as hydrostatic, operational, electrical and functional.
Operational tests will involve actual operation of the system and equipment under design conditions, or simulated design conditions. Functional tests will verify that the system or equipment is capable of performing the func-tion for which it is designed. A summary of the prefueling test program is given in Table 13-1.
13.2 INITIAL CRITICALITY Fuel loading will begin when all prerequisite unit tests and operations have been satisfactorily completed. Core components will be loaded in a predeter- ,
mined sequence. Changes in core suberitical multiplication will be measured l and evaluated; a detailed checkoff list will be followed; and periodic checks made to insure proper status of all equipment, conditions and core components.
Initial criticality will take place by control rod withdrawal and core boron i concentration adjustment.
13.3 POSTCRITICALITY TESTS A series of posteriticality tests will be conducted at ambient and hot zero power and at various power levels up to rated power. These tests will be used to evaluate temperature, pressure, power and boron reactivity coeffi-cients; control rod reactivity worths; the reactivity worth of xenon-135; and core reactivity depletion versus burnup. The reactor coolant system flow will be evaluated and the external and incore nuclear instrumentation systems calibrated at various power levels. The unit response characteristics to step and ramp load changes will be evaluated and adjustments made to the con-trol systems as required. A complete shield survey will be conducted. Field analysis and a more detailed office analysis of test results will be made.
A summary of the posteriticality tests is given in Table 13-2. ,
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- Prefueling Test Program i
Type of Test Opera- Elec- Func-
- Hydro tional trical tional
- 1. Reactor Building and Penetrations '
Leak Rate Test x l
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- 2. Electrical Systems Continuity x l
- 3. Control Rod Drive Assemblies x x x l
- 4. Reactor Building and Component '
l Cooling System x x x !
- 5. Recirculated Cooling Water System x x x
- 6. Reactor Building Spray System x x x )
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- 7. Cooling Water Systems x x x
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- 8. Low Pressure Injection and Decay Heat Removal System x x x x
- 9. Quench Tank x x
- 10. Reactor Coolant System Relief Valves x x
- 11. Chemical Addition and Sampling System x x x
- 12. High Pressure Injection ard Purifica-tion System x x x x
- 13. Reactor Coolant Pumps x x x
- 14. Nuclear Instrumentation Cable Tests x
- 15. Nuclear Instrumentation and Protec-tive Systems x x
- 16. Integrated Reactor-Boiler-Turbine Control System x x
- 17. Reactor and Auxiliary Systems Nonnuclear Instrumentation x x x
- 13. Reactor Coolant System x
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s 19. Reactor Coolant System Hot Func-tional Test x x x 13-2
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Table 13 continued Type of Test Opera- Elec- Func-Hydro tional trical tional
- 20. Reactor Building Fuel Handling System x x x
- 21. Fuel Handling and Storage Area Fuel Handling System x x x
- 22. Area Radiation Monitoring Systems x x
- 23. Incore Instrumentation System x x x
- 24. Waste Disposal System x x x
- 25. Spent Fuel Cooling System x x x
- 26. Emergency Power Systems Tests x x x
- 27. Initial Fuel Loading x
$T. CcRE ft.coONVG $yST M K h A Table 13-2 Posteriticality Test Program
- 1. Initial criticality and Excess Reactivity
- 2. Reactivity Coefficients and Rod Worths
- 3. Stuck Rod Margin Verification
- 4. Power Coefficient and Power Defect
- 5. Reactivity Coefficients at Power
- 6. Xenon Reactivity Worths .
- 7. Reactor Coolant System Flow Test
- 8. Incore and External Nuclear Instrumentation Calibration
- 9. Unit Load Steady State and Transient Tests
- 10. Biological Shield Survey
- 11. Unit Loss-of-Electrical-Load Tests
- 12. Core Reactivity Depletion Rate Versus Burnup 13-3 ,,,.
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