ML19150A494
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GINNA/UFSAR 14 INITIAL TEST PROGRAM 1 14.1
SUMMARY
OF TEST PROGRAM AND OBJECTIVES 2 14.1.1 STARTUP AND POWER TESTING AT 1300 MEGAWATTS THER- 2 MAL 14.1.1.1 Summary 2 14.1.1.2 Tests Prior to Reactor Fueling 3 14.1.1.2.1 Summary 3 14.1.1.2.2 Test Objectives 4 14.1.1.3 Final Plant Preparation 10 14.1.1.3.1 Core Loading 10 14.1.1.3.2 Postloading Tests 11 14.1.1.4 Initial Testing in the Operating Reactor 12 14.1.1.4.1 General 12 14.1.1.4.2 Initial Criticality 12 14.1.1.4.3 Zero Power Testing 12 14.1.1.4.4 Power Level Escalation 13 14.1.1.4.5 Post Startup Surveillance and Testing Requirements 13 14.1.2 POWER TEST PROGRAM TO 1520 MEGAWATTS THERMAL 14 REFERENCES FOR SECTION 14.1 15 Table 14.1-1 INITIAL TESTING
SUMMARY
- INITIAL CRITICALITY 16 THROUGH 100 - HOUR ACCEPTANCE TEST 14.2 INITIAL ORGANIZATION AND STAFFING 19 14.2.1 INITIAL STARTUP AND OPERATING STRUCTURE 19 14.2.2 ONSITE TRAINING PRIOR TO STARTUP 19 14.3 TEST PROCEDURES 21 14.3.1 PRE FUEL LOADING TESTS 21 14.3.2 POST FUEL LOADING TESTS 21 14.4 CONDUCT OF TEST PROGRAM 22 14.4.1 CONDUCT OF INITIAL TEST PROGRAM 22 14.4.2 REVIEW, EVALUATION, AND APPROVAL OF TEST RESULTS 23 14.4.3 TEST RECORDS 23 Page 1 of 6 Revision 28 5/2019
GINNA/UFSAR 14.5 TEST PROGRAM SCHEDULE 24 14.5.1 INITIAL CRITICALITY TO ACCEPTANCE 24 14.5.2 1520 MEGAWATTS THERMAL POWER TEST PROGRAM 25 14.6 INDIVIDUAL TEST DESCRIPTIONS 26 14.6.1 INITIAL STARTUP AND POWER TEST PROGRAM 26 14.6.1.1 Safety Injection Systems Preoperational Tests 26 14.6.1.1.1 Safety Injection Test 26 14.6.1.1.2 Accumulator Blowdown Test 30 14.6.1.1.3 Safety Injection Flow Test 33 14.6.1.1.4 Containment Spray System Test 34 14.6.1.1.5 Residual Heat Removal System Test 34 14.6.1.1.6 Safeguards Systems Operational Test 34 14.6.1.1.7 Emergency Diesel Generator Test 35 14.6.1.1.8 Direct Current Test 36 14.6.1.2 Preoperational Instrumentation and Control Tests 36 14.6.1.2.1 Reactor Coolant System Pressure Comparison Test 36 14.6.1.2.2 Resistance Temperature Detector Cross Calibration Test 36 14.6.1.2.3 Steam Generator Manual Control and Level Instrumentation Test 37 14.6.1.2.4 Rod Position Indication System Test 37 14.6.1.2.5 Rod Stepping Test 38 14.6.1.2.6 Rod Cluster Control Assembly Drop Time and Partial Length Rods 38 Operational Tests 14.6.1.2.7 In-Core Thermocouples Test 38 14.6.1.2.8 Movable In-Core Detector System Test 38 14.6.1.2.9 Reactor Makeup Blender and Boric Acid Transfer Pumps Operational 38 Test 14.6.1.2.10 Pressurizer Level Control Test 39 14.6.1.2.11 Pressurizer Pressure Control Test 40 14.6.1.2.12 Steam Dump Test 41 14.6.1.2.13 Radiation Monitoring System Operational Test 41 14.6.1.2.14 Reactor Coolant System Flow Measurement Test 42 14.6.1.2.15 Nuclear Instrumentation Test 42 14.6.1.3 Safety and Relief Valve Tests 42 Page 2 of 6 Revision 28 5/2019
GINNA/UFSAR 14.6.1.3.1 Pressurizer Safety Valve Test 42 14.6.1.3.2 Main Steam Safety Valve Test 42 14.6.1.4 Waste Systems Tests 43 14.6.1.4.1 Liquid Waste Concentration Demonstration Test 43 14.6.1.4.2 Waste Disposal System Gaseous Waste Test 43 14.6.1.4.3 Liquid Waste Processing Test 44 14.6.1.5 Reactor Coolant System Measurement Tests 44 14.6.1.5.1 Reactor Vessel Internals Measurement Test 44 14.6.1.5.2 Reactor Coolant System Vibration Test 46 14.6.1.5.3 Preoperational Reactor Coolant System Leakage Test 46 14.6.1.5.4 Reactor Coolant System Thermal Expansion Test 47 14.6.1.5.5 Flow Coastdown Test 47 14.6.1.5.6 Natural Circulation Test 47 14.6.1.6 Miscellaneous Safety-Related Tests 48 14.6.1.6.1 Backfeed from the 115-Kilovolt Grid Test 48 14.6.1.6.2 Blackout Test Without Safety Injection Test 49 14.6.1.6.3 Main Steam Isolation Valve Test 49 14.6.1.6.4 Fire Service Water Test 50 14.6.1.6.5 Electrical System Logic Test 50 14.6.1.6.6 Reactor Trip System (RTS) Operational Test 50 14.6.1.6.7 Reactor Coolant System Hydro Test 51 14.6.1.6.8 Ventilation Systems Test 51 14.6.1.6.9 Preoperational Containment Vessel Leak Rate Test 51 14.6.1.6.10 Structural Integrity Test 52 14.6.1.6.11 Reactor Trip System (RTS) Operation Time Response Test 53 14.6.1.7 Operational and Transient Tests 53 14.6.1.7.1 Ten Percent Load Swing Test at Thirty Percent Power 53 14.6.1.7.2 Generator Trip Test 54 14.6.1.7.3 Ten Percent Load Swing Test at Seventy-Five Percent Power Level 54 14.6.1.7.4 Fifty Percent Load Reduction from Seventy-Five Percent Power Level 54 Test 14.6.1.7.5 One Hundred Percent Power Level Transient Tests 55 Page 3 of 6 Revision 28 5/2019
GINNA/UFSAR 14.6.1.7.6 Operational Dynamic Rod Drop Test 57 14.6.1.7.7 Delta T Zero Power Alignment and Delta T Channel Span Adjustment 58 Tests 14.6.1.7.8 Nuclear Instrumentation Calibration and Reactor Coolant System Flow 58 Confirmation 14.6.1.7.9 Ex-Core In-Core Calibration Test 61 14.6.1.8 Startup Physics Testing 61 14.6.1.8.1 Introduction 61 14.6.1.8.2 Power Distribution Measurements 62 14.6.1.8.3 Zero Power Critical Boron Concentrations 62 14.6.1.8.4 Reactivity Coefficients and Shutdown Margin 62 14.6.1.8.5 Ejected and Dropped Rod Worths 62 14.6.1.8.6 Xenon Oscillation Test 62 14.6.2 POWER TEST PROGRAM TO 1520 MEGAWATTS THERMAL 63 14.6.2.1 Test Description 63 14.6.2.2 Steam Generator Moisture Carryover Tests 65 14.6.2.3 Assembly Delta T Measurements 65 14.6.2.4 Plant Radiation Surveys 65 14.6.2.5 Reactor Physics Measurements 66 14.6.2.5.1 Zero Power Measurements 66 14.6.2.5.2 At-Power Measurements 66 Table 14.6-1a ACCUMULATOR BLOWDOWN TEST RESULTS - OBSERVED 69 RESULTS Table 14.6-1b ACCUMULATOR BLOWDOWN TEST RESULTS - PREDICTION 70 OF FINAL PRESSURE Table 14.6-1c ACCUMULATOR BLOWDOWN TEST RESULTS - PIPE RESIS- 71 TANCE Table 14.6-2 BEGINNING OF CYCLE ZERO POWER CRITICAL BORON CON- 72 CENTRATIONS Table 14.6-3 REACTIVITY COEFFICIENTS AND SHUTDOWN MARGIN 73 Table 14.6-4 EJECTED AND DROPPED ROD WORTHS 74 Table 14.6-5 AVERAGE INCREASE IN CONTAINMENT RADIATION LEVELS 75 DURING UPRATING PROGRAM TO 1520 MEGAWATTS THER-MAL Table 14.6-6
SUMMARY
OF MEASURED PARAMETERS AT HOT ZERO 76 POWER PRIOR TO UPRATING TO 1520 MEGAWATTS THERMAL Page 4 of 6 Revision 28 5/2019
GINNA/UFSAR Table 14.6-7 SELECTED DATA FOR FLUX MAPS 77 FIGURES Figure 14.2-1 Initial Plant Organization Figure 14.6-1 Original Safety Injection System Functional Test Data Sheet (Typical)
Sheet 1 -
Figure 14.6-1 Original Safety Injection System Functional Test Data Sheet (Typical)
Sheet 2 -
Figure 14.6-2 Rod Cluster Control Assembly Drop Time Test Results (Typical)
Sheet 1 -
Figure 14.6-2 Rod Cluster Control Assembly Drop Time Test Results (Typical)
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Figure 14.6-2 Rod Cluster Control Assembly Drop Time Test Results (Typical)
Sheet 3 -
Figure 14.6-2 Rod Cluster Control Assembly Drop Time Test Results (Typical)
Sheet 4 -
Figure 14.6-3 Partial-Length Rods Operation Test Results (Typical)
Figure 14.6-4 Radiation Monitoring System Operational Test Data Sheet (Typical)
Sheet 1 -
Figure 14.6-4 Radiation Monitoring System Operational Test Data Sheet (Typical)
Sheet 2 -
Figure 14.6-5 Pressurizer Safety Valve Test Data Sheet Figure 14.6-6 Reactor Vessel Internals Displacement Indicators Figure 14.6-7 Reactor Vessel Accelerometers Sheet 1 -
Figure 14.6-7 Reactor Vessel Accelerometers Sheet 2 -
Figure 14.6-7 Reactor Vessel Accelerometers Sheet 3 -
Figure 14.6-7 Reactor Vessel Accelerometers Sheet 4 -
Figure 14.6-8 Reactor Coolant System Vibration Test Data Sheet Sheet 1 -
Figure 14.6-8 Reactor Coolant System Vibration Test Data Sheet Sheet 2 -
Figure 14.6-9 Reactor Coolant Pump Flow Coastdown Test Sheet 1 -
Figure 14.6-9 Reactor Coolant Pump Flow Coastdown Test Sheet 2 -
Figure 14.6-9 Reactor Coolant Pump Flow Coastdown Test Sheet 3 -
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GINNA/UFSAR Figure 14.6-9 Reactor Coolant Pump Flow Coastdown Test Sheet 4 -
Figure 14.6-9 Reactor Coolant Pump Flow Coastdown Test Sheet 5 -
Figure 14.6-10 Natural Circulation Test Data Sheet 1 -
Figure 14.6-10 Natural Circulation Test Data Sheet 2 -
Figure 14.6-11 Preoperational Containment Leak Rate Test Data Figure 14.6-12 Preoperational Containment Leak Rate Test, Pressurization System Figure 14.6-13 50% Load Reduction From 75% Power Level Test, Recorded Process Sheet 1 - Variables Figure 14.6-13 50% Load Reduction From 75% Power Level Test, Recorded Process Sheet 2 - Variables Figure 14.6-13 50% Load Reduction From 75% Power Level Test, Recorded Process Sheet 3 - Variables Figure 14.6-13 50% Load Reduction From 75% Power Level Test, Recorded Process Sheet 4 - Variables Figure 14.6-13 50% Load Reduction From 75% Power Level Test, Recorded Process Sheet 5 - Variables Figure 14.6-14 Operational Dynamic Rod Drop Test, Nuclear Power Channel Signals Figure 14.6-15 Ginna 1520 Megawatts Power Test Program, March 1 Through April 15, 1972 Figure 14.6-16 Ginna Uprating, Control Bank D Differential and Integral Worth, Cycle 1B 7800 MWd/MTU, Hot Zero Power Figure 14.6-17 Ginna Uprating, Control Bank C Differential and Integral Worth, Cycle 1B 7800 MWd/MTU, Hot Zero Power Figure 14.6-18 Ginna Uprating, Boron Concentration Versus Reactivity Insertion, Cycle 1B 7800 MWd/MTU, Hot Zero Power Figure 14.6-19 Ginna Uprating, Isothermal Temperature Coefficient Versus Boron Concentration, Cycle 1B 7800 MWd/MTU, Hot Zero Power Figure 14.6-20 Relative Power During Uprating: 1300, 1380, 1455 MWt Figure 14.6-21 Relative Power During Uprating: 1455 MWt Figure 14.6-22 Ginna Uprating, Power Range Output Versus Core Power, Channel NE41 Figure 14.6-23 Ginna Uprating, Axial Offset Calibration, Channel 41 Output Normal-ized to 1520 MWt Figure 14.6-24 Relative Power at 1520 MWt, April 12, 1972 Page 6 of 6 Revision 28 5/2019