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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML20056D3951993-08-0909 August 1993 Rev 04.01 to Procedure 41AO-1ZZ08, SG Tube Leak ML20056D3961993-06-16016 June 1993 Rev 00.07 to Procedure 41EP-1R004, Excess Steam Demand, Consisting of CRS Actions & Details on Emergency Notification & Support ML20056G0111993-03-21021 March 1993 Rev 7 to Odcm ML17306A9831992-09-0303 September 1992 Window 2B08B, Rc LO Temp Over Press of Rev 5 to Procedure 40AL-9RK2B ML17306A9841992-09-0303 September 1992 Window 2B08B, SDC Ln Isol VLV Not Fully Closed of Rev 5 to Procedure 40AL-9RK2B ML17306A9851992-09-0303 September 1992 Window 2B09A, SDC Ln Isol Vlvs UV-653/654 Inverter Trbl of Procedure 40AL-9RK2B ML17306A9871992-09-0303 September 1992 Window ES2A01B, LO Press Safety Inj of Rev 2 to Procedure 41AL-1ES2A ML17306A4741991-10-30030 October 1991 Rev 2 to Nuclear Administrative & Technical Manual 76PR-9RW01, Solid Radwaste Process Control Program. ML20085L3671991-10-28028 October 1991 Emergency Response Data Sys (ERDS) Implementation Program Plan for Palo Verde Nuclear Generating Station ML17305B5521991-01-31031 January 1991 Rev 6 to Salt Deposition & Impact Monitoring Plan for Palo Verde Nuclear Generation Stations,Units 1,2 & 3. ML17305B2731990-07-31031 July 1990 PVNGS 1991 Business Plan. ML17306A5181989-10-22022 October 1989 Rev 0 to Nuclear Administrative & Technical Manual 01PR-0QQ02, Employee Concerns Program Policy. ML17306A5161989-09-28028 September 1989 DOL000483, Employee Concerns Program. ML20127J4161989-03-0808 March 1989 Procedure 2-3-89-001, Safety Equipment Status Sys ML20082D9681989-01-18018 January 1989 Rev 1 to Nuclear Administrative & Technical Manual 81AC-OCC07, Cable & Raceway Control & Tracking Sys ML20082D9721988-08-19019 August 1988 Rev 0 to Administrative Change Notice 03 to ES03.03, Cable & Raceway Control & Tracking Sys ML20082E6001988-07-11011 July 1988 Rev 0 to Administrative Change Notice 02 to ES03.03, Cable & Raceway Control & Tracking Sys ML20082D9801988-06-21021 June 1988 Rev 2 to QA02.02, QC Insps ML20082D9871988-06-0202 June 1988 Rev 0 to ES10.00, Sys Engineer Program ML20082D9901988-05-26026 May 1988 Rev 7 to 73AC-OZZ29, Engineering Evaluation Request ML20082E6221988-05-19019 May 1988 Rev 0 to Administrative Change Notice 01 to ES03.03, Cable & Raceway Control & Tracking Sys ML17304A1651988-05-10010 May 1988 Loose Part Monitoring Sys Loose Part Detection Program Rept. W/Eleven Oversize Drawings ML20082E6291987-09-0202 September 1987 Rev 0 to ES03.03A, Cable & Raceway Control & Tracking Sys ML20237H5571987-08-0303 August 1987 Public Version of Revs to Emergency Plan Implementing Procedures,Including Temporary Procedure Change Notice (Tpc) 3 to Rev 5 to EPIP-02, Emergency Classification & Tpc Notice 2 to Rev 11 to EPIP-03.W/870820 Release Memo ML20235X0961987-07-0202 July 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 3 to EPIP-56, UHS Emergency Water Supply, Rev 4 to EPIP-33, Offsite Assistance & Rev 5 to EPIP-27, Post-Accident Sampling Analysis ML17300A7801987-04-16016 April 1987 Procedure Change Notice 1 to Rev 0 to Procedure 41AO-1ZZ54, Monitoring Reactor Vessel Inventory W/Reactor Vessel Level Monitoring Sys Inoperable. W/870416 Ltr ML17303A3611987-03-20020 March 1987 Test/Retest Recovery Program Diesel Generator B & Associated Support Equipment. ML17333A1801987-03-13013 March 1987 Diesel Generator B Test Insps. ML20206N4501987-03-0606 March 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure Change Notice 02 to Rev 5 to EPIP-02, Emergency Classification, Closing Out Open Item Noted by NRC ML20212M8121987-01-28028 January 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 11 to EPIP-04 Re Alert,Site Area & General Emergency Implementing Action,Consisting of Temporary Change Notice 02T ML20214U1761986-09-11011 September 1986 Public Version of Procedure Change Notice 3 to Rev 10 to Emergency Plan Implementing Procedure EPIP-3, Notification of Unusual Event Implementing Actions. W/860925 Release Memo ML20205E5391986-07-29029 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 4 to EPIP-23, Fire Fighting, Rev 5 to EPIP-02, Emergency Classification & Rev 11 to EPIP-04, Alert,Site Area.. ML20211Q5951986-07-10010 July 1986 Public Version of Rev 10 to EPIP-03, Notification of Unusual Event Implementing Actions & Rev 4 to EPIP-15, Protective Action Guidelines. W/Procedure Change Notices 1 & 2 to EPIP-03 ML20212N2671986-07-0303 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 5 to EPIP-02, Emergency Classification & Rev 10 to EPIP-03, Notification of Unusual Event Implementing Actions ML17300A3731986-06-25025 June 1986 Rev 0 to Pump & Valve Inservice Testing Program, for Units 1,2 & 3 ML17300A2611986-05-29029 May 1986 Rev 0 to Inservice Insp Program Summary Manual. ML20155K1011986-04-17017 April 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 10 to EPIP-03 Re Notification of Unusual Event Implementing Actions & Rev 9 to EPIP-04 Re Alert Implementing Actions.W/Grimsley 860521 Release Memo ML20206E5991986-04-0808 April 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Index,Cancellation of Rev 2 to EPIP-28, Personnel Monitoring & Decontamination & Cancellation of Rev 2 to EPIP-29 ML17299B1791986-03-11011 March 1986 Public Version of Revised Emergency Plan Implememting Procedures EPIP 11,EPIP 19 & EPIP 20 & Revs 1 to Administrative Procedures 7N409.08.00 & 7N409.09.00, respectively.W/860409 Release Memo ML17299B0501986-02-21021 February 1986 Rev 2 to Operations Procedure 42AO-2ZZ50, Venting Charging Pumps. 1999-07-14
[Table view] |
Text
Rev. 1 2/29/S4 REACTOR COOLANT SYSTEM DEMONSTRATION TEST 1.0 The primary objectives of the 'Reactor Coolant System Demonstration Test are as follows:
1.1 To verify the adequacy of the modification to the Upper Guide Structure (UGS).
1.2 To verify the adequacy of the modification to the four main Reactor Coolant Pumps.
1.3 To verify the adequacy of the redesign of the Reactor Coolant System Thermowells.
1.4 To measure and determine the Reactor Coolant System pump flow rates as follows:
1.4.1 Using Ultra Sonic flow measuring equipment 1.4.2 Using a high speed data logger (TDAS) to measure and record the RC pump delta pressures during coast down tests 1.5 To record, for baseline data, various Reactor Coolant Pump temperature, pressure and flows for all four RCP's on a continuous basis.
1.6 To record for baseline data on a continuous basis Reactor Coolant System and supporting plant system parameters. i.e.;
1.6.1 Nuclear Cooling Water temperatures 1.6.2 Nuclear Cooling Water flows 1.63 Seal injection flows 1.64 Seal injection temperatures 1.7 To collect data for a minimum of 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of four (4) pump steady-state, operation at a RCS temperature of 565 + 5'F and 2250 + 15 psia.
1.7.1 CE has determined through analysis of the Precritical Vibration Analysis Program (PVAP) data obtained from the Hot Functional testing that the primary forcing function frequency driving the UGS is approximately 14 Hz.
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Rev. 1 2/29/84 1.7.2 Per Nuclear Regulatory Guide 1.20 requirements "to obtain sufficient vibratory cycles on all components" within the UGS at a forcing function frequency of 14 hertz then the time required equals:
50,400 cycles/hr 8 14Hz rate 198.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2.0 Method to Obtain and Verify Objectives 2.1 Four major instrumentation test stations are being assembled to acquire and record data from both permanent plant instruments and temporarily installed instruments.
The permanent plant instruments will be used to provide baseline data on a continuous basis.
The temporary instrumentation will be used to verify the pump modifications, the UGS modifications and the thermowell redesign.
The temporary instruments can be categorized as follows:
2.1.1 Accelerometers 2.1.2 High Frequency Pressure transducers 2.1.3 Strain gauges 2.1.4 Ultra-sonic crystals 2.1.5 Suction pressure pressure transducers 2.2 Recording instrumentation 2.2.1 Thirteen 8 channel strip chart recordersit 2.2.2 Five, 14 channel FM magnetic tape recorders 2.2.3 Micro-processor controlled data'oggers 2.2.3.1 PERM DAS Permanent Data Acquisition System i
- 2. 2. 3. 2 DART Data Acquisition and Retrievable Termi nal 2.2.3.3 TDAS Temporary Data Acquisition System
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Rev. 1 2/29/S4 2.3 Temporary Reactor Coolant System Pump Instruments 2.3.1 A tri-axial accelerometer mounted on the thrust bearing assembly on each of the four RCP's will monitor vibration/motion transferred from the pump/impeller through the pump shaft to the thrust bearing.
2.3.2 Three high frequency pressure transducers will measure the pressure pulses caused by the impeller vanes. Both frequency and amplitude of the pulses will be obtained and recorded:
These pressure pulse signals will also be routed to the UGS instrumentation test station so that the relationship between the pump pressure pulses and vibration and strain occurring within the UGS can be determined.
2.3.3 Three (3) tri-axial accelerometers, magnetically mounted on two of the cold legs and on Hot Leg 1 will measure pump induced vibrations of the RCS piping.
2.3.4 Four pressure transducers are being installed to measure the pump suction pressure for each of the Reactor Coolant pumps to verify adequate suction head pressure is present any time the pumps are in operation.
2.3.5 The Ultra-sonic crystals will be mounted on Hot Leg 1 and 2 to be used with the Ultra-sonic flow measuring equipment to determine the RCP flows for the system.
2.4 Thermowell Instrumentation 2.4.1 Three thermowells will have internally mounted bi-axial accelerometers to measure the motion of the thermowells caused by the pump pressure pulses. One of the thermowell outer nozzles will also have a bi-axial accelerometer to measure motion at the outer connector-head location to determine if any vibratory motion is being induced external to the RCS piping.
2.5 UGS Instrumentation 2.5.1 Nine bi-axial accelerometers are mounted in and on the tubes within the UGS to monitor vibration.
2.5.2 Seven high frequency pressure transducers are also mounted with the tubes to measure pressure pulses occurring in the tubes.
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- 2. 5.3 Eighteen (18) strain gauges are mounted on the tubing and webbing within the UGS particularly in those areas where damage was found after the Hot Functional test.
3.0 Procedures 3.1 Controlling and Sequencing 3.1.1 The Reactor Coolant System Test Procedure 91HF-1RC17 has been written to control, sequence and coordinate data acquisition by the instrumentation test stations personnel and equipment as a fifty (50) test step sequence is performed to verify the test objectives and begin a 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> steady-state four pump run.
3.2 Implementing Procedures 3.2.1 Three implementing procedures have been written to provide a defined and controlled data acquisition system at each of the major test stations. These procedures are as follows:
3.2.1.1 UGS Modification Verification 91HF-1RC18 3.2.1.2 RCS Pump Data, Operating 6 Continuous Monitoring 3.2.1.3 Pre-Core RCS Flow Rate 91HF-lRC03, Rev. l.
3.3 Pre and Post-test Inspection RV.
3.3.1 The pre-inspection procedure will be a visual inspection with photographs.
3.3.2 The post-test inspection will occur after the Demonstration Test has been completed and Reactor Vessel is disassembled.
3.4 Post-test Inspection Reactor Coolant Pump 3.4.1 At least one RCP will be disassembled and inspected for wear, damage, cracking, and cavitation effects after the RCS has been vented, cooled down, and drained.
4.0 Pre-Test Initial Conditions The Pre-Core Hot Pump Test Controlling Document, 91HF-1ZZ05 f'.1 will define and control operating support systems, valve line-ups and maneuver the plant to the pressure and temperature plateaus
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Rev. 1 2/29/84 required by the Reactor Coolant System Demonstration Test Procedure 91HF-1RC17. The Demonstration Test Director will control the Reactor Coolant pump starts, stops, and steady-state pump combinations required to reach the four pump 200 hour steady state run.
4.2 The initial temperature and pressure plateau is 150'F and 360-375 psia.
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This allows fill and vent, pressurizer bubble 5.0 Temperature and Pressure Bar-graph Explanation 5.1 there are seven (7) basic temperature steps denoted by the bar graph as follows:
5.1.1 150'F + O' 5.1.2 200'F + 5'F 5.1.3 260'F + 5'F 5.1.4 360 F + 5'F
- 5. 1. 5 500'F + 5'F 5.1.6 550'F + 5 F 5.1.7 565'F + 5'P and 565'F + 0.5'F The 565'F + 0.5'F is maintained during the ultrasonic flow measurements.
5.2 There are four (4) basic pressure plateaus denoted by the bar graph as follows:
5.2.1 360 375 psia 5.2.2 360 - 390 psia 5.2.3 1485 - 1515 psia 5.2.4 2235 2265 psia
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- 5. 3 Bar graph numbering 5.3.1 The numbers written above the bar graph plateaus such as 6- -16, 17 for temperature plateau 255 265'F (written below the bar) indicates those Test Sequences being performed in order at that temperature (and also pressure).
5.4 Test Step Summary (145-155'F, 360-375 psia) 5.4.1 Test Steps 1 5 will monitor the following:
5.4.1.1 Internal/External thermowell vibration 5.4.1.2 Pump vibration and shaft orbit data.
5;4.1.3 RCS pipe motion 5.4.1.4 UGS vibration, pressure and strain 5.4.1.5 Pump pressure pulsations 5.4.1.6 Pump suction pressure 5.4.2 Test Steps 6 17 (255 265'F, 360 375 psia) 5.4.2.1 Pump vibration and,orbit data Y
5.4.2.2 RCS pipe motion 5.4.2.3 UGS Vibration, pressure, and strain 5.4.2.4 Pump pressure pulsations 5.4.2.5 Pump suction pressure Various single, dual and three pump configurations are provided during these test sequences, including start, stop, and steady-state conditions.
5.4.3 Test Steps 17 19 (355 365'F, 360 390'sia) 5.4.3.1 Pump vibration and orbit data 5.4.3.2 RCS pipe motion
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Rev. 1 2/29/84 5.4.3.3 Pump pressure pulsations 5.4.3.4 Pump suction pressure 5.4.4 Test Steps 20 25 (495 505'FF, 1485 1515 psia) 5.4.4.1 Pump vibration and orbit data 5.4.4.2 RCS pipe motion 5.4.4.3 Pump pressure pulsations 5.4.4.4 Pump suction pressure 5.4.4.5 UGS vibration, pressure, strain 5.4.5 Test Steps 25 39 (545 555'F, 2235 2265'sia) 5.4.5.1 Pump vibration and orbit data 5.4.5.2 RCS pipe motion 5.4.5.3 Pump pressure pulsations 5.4.5.4 Pump suction pressure 5.4.5.5 UGS vibration, pressure, strain (UGS data completed at test step 39).
5.4.6 Test Steps 39-1 49 (560 570'F or 564.5 565.5'F 8 2235 2265'sia)
These test steps are primarily for determining the RCS combined flows using the Ultra-Sonic Flow Measuring equipment. Some of the Test Steps are used to maneuver the pump combinations for 4 pump steady-state flow, no flow (all pumps off) and coast downs (RCP delta-pressure measurements) two pump combination. When flow data is being collected by ultra-sonics the temperature must be very stable. This is the reason for the 565 + 0.5'F tolerance.
5.4.7 After the successful completion of all test steps through and including 49, the RCS will begin the 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> 4 pump steady-state run. Data will continue to be taken on a once-per-shift basis; however, all test stations will be manned in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> continuous basis to monitor for any unsafe condition or any parameter trending towards an out-of-limit condition.
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