ML20141K946
| ML20141K946 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/27/1997 |
| From: | Gilbert J, Von Suskil J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20141K945 | List: |
| References | |
| NUDOCS 9706020155 | |
| Download: ML20141K946 (21) | |
Text
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l PECO NUCLEAR 1
Limerick Generating Station
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i Unit 2 l
l Startup Test Report t
Cycle 5
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l Preparation Directed by:
J. D. von Suskil, Director - Site Engineering Prepared by:
J. B. Gilbert, II,' Reactor Engineering i
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l 9706020155 970527 ,
i PDR ADOCK 05000353
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- 7. Limerick Generating Station i Unit 2 Startup Test Report Page 2 of 21
[ JBG:sja TAHLE OF CONTENTS Section Title Pace 1.0
SUMMARY
4 1.1 Puipose 4 1.2 Acceptance Criteria 4 1.3 Test Requirements 4 2.0 UFSAR CilAPTER 14.2 TESTS NOT REQUIRED 5 2.1 STP-9, Water Level Reference Leg Temperature 5 i
2.2 STP-13, Plant Monitoring System 5 2.3 STP-14, Reactor Core Isolation Cooling System 5 2.4 STP-15, High Pressure Coolant Injection System 5 2.5 STP-16, Selected Process Temperatures 6 2.6 STP-17, System Expansion 6 2.7 STP-20, Steam Production 6 2.8 STP-22, Pressure Regulator 6 2.9 STP-23, Feedwater System 7 2.10 STP-24, Turbine Valve Surveillance 7 1 2.11 STP-25, Main Steam isolation Valves 7 2.12 STP-26, Relief Valves 7 j 1
2.13 STP-27, Main Turbine Trip 7 l 2.14 STP-28, Shutdown From Outside the Main Control Room 8 j 2.15 STP-29, Recirculation Flow Control System 8 l l
2.16 STP-30, Recirculation System 8 2.17 STP-31 Loss of Turbine Generator and Offsite Power 8 2.18 STP-32, Essential llVAC System Operation and Containment l Hot Penetration Temperature Verification 8 1
l 2.19 STP-33, Piping Steady State Vibration 9 2.20 STP-34, Offgas Performance Verification 9
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t- .- Limerick Generating Station Unit 2 Startup Test Report Page 3 of 21 JBG:sja Section Title Pace 2.21 STP-35, Recirculation System Flow Calibration 9 2.22 STP-36, Piping Dynamic Transients 10 2.23 STP-70, Reactor Water Cleanup System 10 2.24 STP-71, Residual lleat Removal System 10 3.0 UFSAR CHAPTER 14.2 TESTS REQUIRED 11 3.1 STP-1, Chemical and Radiochemical 1i 3.2 STP-2, Radiation Measurements 12 3.3 STP-3, Fuel Loading 13 3.4 STP-4, Shutdown Margin Demonstration 14 3.5 STPS, Control Rod Drive System 15 3.6 STP-6, SRM Performance and Control Rod Sequence 16 3.7 STP-10, IRM Performance 17 3.8 STP-11, l.PRM Calibration 18 -
3.9 STP-12, APRM Calibration 19 ,
l 3.10 STP-18, TIP Uncertainty 20 I
3.11 STP-19, Core Performance 21 I 1
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Limerick Generating Station 1 Unit 2 Startup Test Report 1 Page 4 of 21 JBG:sja 1.0
SUMMARY
l This Startup Test Report is submitted to the Nuclear Regulator Commission (NRC) in accordance with the requirements of Limerick Generating Station (LGS) Technical Speci6 cations (TS) 6.9.1.1 through 6.9.1.3.
The report summarizes the startup testing performed on LGS Unit 2 following installation of fuel of a -
different design during the Fourth Unit 2 Refueling Outage (2R04). All testing identified within the LGS Updated Final Safety Analysis Report (UFSAR) Chapter 14.2 is addressed and evaluated for applicability to the change in fuel type as required by TS.
The Reactor Mode Switch was placed in the startup position on February 26,1997. The Gnal synchronization to the grid was performed on February 28,1997, marking the official end to the Unit 2 fourth refueling outage. The Unit reached full power operation on March 3,1997.
This is the first application of a reload quantity of General Electric gel 3 fuel for LGS Unit 2. GE13 fuel was previously loaded into Unit 1. GE13 is very similar Ao gel 1 (9x9). gel 3 fuel has part length rods 12 inches longer than GElI,2 kg more uranium than GElI and one more fuel pin spacer grid than Gell.
GE13 fuel has up to 5% more critical power margin than Gell and has 0.8 psi larger bundle delta-P than gel I which will require increased recirculation pump speed. GE13 also required a TS Safety Limit CPR change, gel 3SLCPR = 1.11. 284 bundles of GE13 have been loaded into Cycle 5.
The successfully implemented startup program ensures that 2R04 has resulted in no conditions or system characteristics that diminishes the safe operation of the plant. The tests and data referenced in this report
- are on file at the LGS.
- 1. I PURPOSE The Startup Test Report summarizes the testing performed on Limerick Generating Station (LGS) Unit 2 following a change in fuel type. Ali testing identined within the LGS UFSAR Chapter 14.2 is addressed and evaluated for applicability to the change in fuel type as required by TS 6.9.1.1. Each test required for a change in fuel type is described in section 3, including the test objective, acceptance criteria, and results.
This report is submitted in accordance with requirements of TS 6.9.l.1. through TS 6.9.1.3.
1.2 ACCEPTANCE CRITERIA Level I acceptance criteria normally relates to the value of a process variable assigned in the design of the l plant, component systems or associated equipment. If a Level I criteria is not satis 6ed, the plant will be ;
put in a suitable hold condition until resolution is obtained. Tests compatible with this hold condition may be continued. Following resolution, applicable tests must be repeated to verify that the requirements of the Level I criteria are now satis 0ed.
Level 2 criteria is associated with expectations relating to the performance of systems. If a Level 2 criteria _
l is not satisfied, operating and testing plans would not necessarily be altered. Investigation of the j l measurements and the analytical techniques used for the predictions would be started.
1.3 TESTING REQUIREMENTS Each of the tests listed in LGS UFSAR Chapter 14.2 were evaluated for applicability to change in fuel type. Section 2 lists the tests not required to be performed for a change in fuel type and the reasons for each detennination. Section 3 lists the tests which are required for a change in fuel type. All tests are numbered as designated in the UFSAR.
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Limerick Generating Station Unit 2 Startup Test Report j Page 5 of 21 JBG:sja j 2.0 UFSAR CilAPTER 14.2 TESTS NOT REQUIRED The gel 3 fuel product line is fully compatible with the co-resident fuel, reactor vessel internals, and other plant systems. NRC approval for the use of GE13 fuel has been granted according to the procedure described in NEDE-32198P,"GE13 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR 11)," December 1993. gel 3 compliance with the fuel licendng criteria set forth in NEDE-240ll-P-A-10,"GESTAR II, General Electric Standard Application for Reactor Fuel," has been demonstrated by the NEDE-32198B analyses; this demonstration constitutes NRC approval of the gel 3 fuel design. The thermal-mechanical, nuclear, and thermal-hydraulic behavior of the gel 3 fuel design during steady-state, transient, and accident conditions in t1 : > a for core complies fully with the fuel design and licensing criteria set forth in NEDE-24011-P-rvlU and in the other applicable portions of the LGS UFSAR. Adherence to these design bases has also been verified for shutdown conditions in the core and spent fuel pool, and during refueling operations. There is no increase in the probability or severity of 1 any accident.
Unless otherwise noted under the specific test, this evaluation establishes that change to the gel 3 fuel l type will not affect perfonnance of systems in section 2. Therefore, the startup tests listed in this section 1 were not required to be re-performed. )
2.1 STP-9, WATER LEVEL REFERENCE LEG TEMPERATURE The objectives of this test are (1) to measure the level instrumentation reference leg temperature, (2) recalibrate the water level instruments if the measured temperature is significantly different from the 3 value assumed during the initial end points calibration, and (3) to obtain baseline data on the Narrow i Range and Wide Range water level instrumentation.
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The new fuel design does not affect the performance of systems needed to satisfy the objectives of this test.
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2.2 STP-13, PLANT MONITORING SYSTEM The objective of this test is to verify the performance of the Plant Monitoring System (PMS) under plant operating conditions.
The PMS has been fully tested at plant operating conditions, the functions of the PMS are not changed due to change in fuel type. The process computer databank, which included gel 3 fuel data, was prepared (by the fuel vendor), reviewed per FM.UG-270, and installed by performance of RT-3-038-360-2 on February i 21,1997. I 2.3 STP-14, REACTOR CORE ISOLATION COOLING SYSTEM The objectives of this test are (1) to verify the proper operation of the Reactor Core isolation Cooling (RCIC) System over its expected operating pressure and flow ranges, and (2) to demonstrate reliability in automatic starting from cold standby when the reactor is at power conditions.
The new fuel design does not affect the performance of systems needed to satisfy the objectives of this test.
I 2.4 STP-15, lilGil PRESSURE COOLANT INJECTION SYSTEM I
The objectives of this test are (1) to verify the proper operation of the liigh Pressure Coolant injection (llPCI) System over its expected operating pressure and flow ranges, and (2) to demonstrate reliability in automatic starting from cold standby when the reactor is at rated pressure conditions.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
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Limerick Generating Station Unit 2 Startup Test Report l Page 6 of 21 j JBG:sja 2.5 STP-16, SELECTED PROCESS TEMPERATURES The objective of this test is to assure that the measured bottom head drain temperature corresponds to
- bottom head coolant temperature during normal operation. <
l l The new fuel design did not affect the performance of systems needed to satisfy the objective of this test.
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2.6 STP-17, SYSTEM EXPANSION This test verines that safety related piping systems and other piping systems as identiGed in the FSAR expand in an acceptable manner during plant heatup and power escalation. Specific objectives are to verify i l that: (1) Piping thermal expansion is as predicted by design calculations;(2) Snubbers and spring hangers -
remain within operating travel ranges at various piping temperatures; and (3) Piping is free to expand without interference.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
l j 2.7 STP-20, STEAM PRODUCTION The objective of this test is to demonstrate that the Nuclear Steam Supply System (NSSS) can provide steam sufGcient to satisiy all appropriate warranties as denned in the NSSS contract.
The new fuel design did not affect the performance of systems needed to satisfy the objective of this test.
2.8 STP-22, PRESSURE REGULATOR 1 1 i The objectives of this test are as follows:
To demonstrate optimized controller settings of the pressure control loop by analysis of the transients induced in the reactor pressure control system by means of pressure regulator set point j changes. l To demonstrate the take-over capability of the back-up pressure regulator upon failure of the controlling pressure regulator, and to set spacing between the setpoints at an appropriate value.
l To demonstrate smooth pressure contro1 transition between the turbine contro'l valves and the bypass valves when reactor steam generation exceeds the steam flow used by the turbine.
To demonstrate the stability of the reactivity-void feedback loop to pressure perturbations in conjunction with STP-21, Core Power Void-Mode Response.
l The new fuel design.did not affect the performance of systems needed to satisfy the objectives of this test.
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2.9 STP-23, FEEDWATER SYSTEM - l The objectives of this test are:
i To demonstrate that the feedwater system has been adjusted to provide acceptable reactor water l level control.
. To demonstrate an adeqm 2esponse to a feedwater temperature reduction, l
To demonstrate the capability of the automatic core flow runback feature to prevent low water ;
level SCRAM following the trip of one feedwater pump at high power operation. j To demonstrate that the maximum feedwater runout capability is compatible with the licensing assumptions.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
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2.10 STP-24, TURBINE VALVE SURVEILLANCE The objectives of this test are to demonstrate acceptable procedures and maximum power levels of periodic surveillance testing of the main turbine control, stop and bypass valves without producing a reactor SCRAM.
The new fuel design did net affect the performance of systems needed to satisfy the objectives of this test.
2.11 STP-25. MAIN STEAM ISOLATION VALVES The objectives of this test are (1) to functionally check the Main Steam Isolation Valves (MSIV's) for proper operation at selected power levels,(2) to determine the MSIV closure times, and (3) to determine the maximum power level at which full closure of a single MSIV can be perfonned without causing a reactor SCRAM. The full isolation is performed to determine the reactor transient behavior that results j
- from the simultaneous full closure of all MSIV's at a high power level.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test. i 2.12 STP-26, RELIEF VALVES 4 i
The objectives of this test are (1) to verify that the Relief Valves function properly (can be manually opened and closed), (2) to verify that the Relief Valves reseat properly after actuation, (3) to verify that there are no major blockages in the Relief Valve discharge piping and (4) to demonstrate system stability to )
Relief Valve operation.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test. !
! 2.13 STP-27, MAIN TURBINE TRIP !
L i The objectives of this test are (1) to determine the response of the reactor system to a turbine trip or l'
- generator load rejection; and (2) to evaluate the response of the bypass, SRV, and the reactor protection j systems.
l The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test. !
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.. Limerick Generating Station Unit 2 Startup Test Report Page 8 of 21 JBG:sja 2.14 STP-28, SliUTDOWN FROM OUTSIDE Tile MAIN CONTROL ROOM The objectives of this test are to demonstrate that the Reactor (1) can be safely shutdown from outside the Main Control Room (MCR), (2) can be maintained in a flot Standby condition from outside the MCR and (3) can be safely cooled from hot to cold shutdown from outside the MCR. In addition, it will provide an opportunity to demonstrate that the procedures of Remote Shutdown are clear and comprehensive and that operational personnel are familiar with their applications.
The change in fuel type does not change the capability of the reactor to be shutdow n from outside the MCR. Therefore, a repeat of this test is not required.
2.15 STP-29, RECIRCULATION FLOW CONTROL SYSTEM The objectives of this test are (1) to demonstrate the flow control capability of the plant over the entire pump speed range, and (2) to determine that the controllers are set for the desired system performance and stability.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
2.16 STP-30, RECIRCULATION SYSTEM The objectives of this test are to:
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Obtain recirculation system performance data during steady-state conditions, pump trip, flow coastdown, and pump restart.
Verify the.t the feedwater control system can satisfactorily control water level on a single recirculation pump trip without a resulting turbine trip and associated SCRAM.
l Record and verify acceptable performance of the circuit of a two-recirculation pump trip. j i
Verify the adequacy of the recirculation runback to avoid a SCRAM upon simulated loss of one feedwater pump. j l Verify that no recirculation system cavitation will occur in the operable region of the power-flow i i map.
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The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
l 2.17 STP-31, LOSS OF MAIN TURBINE GENERATOR AND OFFSITE POWER This test determines electrical equipment and reactor system transient performance during a loss of Main Turbine Generator coincident with loss of all sources of offsite power.
i The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
s S. Limerick Generating Station Unit 2 Startup Test Report Page 9 of 21 JBG:sja 2.18 STP-32, ESSENTIAL liVAC SYSTEM OPERATION AND CONTAINMENT liOT PENETRATIONTEMPERATURE VERIFICATION The objectives of this test are to demonstrate, under actual / normal operating conditions, that the various Heating Ventilation and Air Conditioning (liVAC) systems will be capable of maintaining specified ,
ambient temperatures and relative humidity within the following areas:
Primary Containment (drywell and suppression chamber)
Reactor Enclosure and Main Steam Tunnel MCR Control Enclosure Radwaste Enclosure In addition, this test shall verify that the concrete temperature surrounding Main Steam and Feedwater containment penetrations remains within specified limits.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
2.19 STP-33, PIPING STEADY STATE VIBRATION The objective of this test is to verify that the steady state vibration of Main Steam, Reactor Recirculation and selected BOP piping systems is within acceptable limits.
The new fuel design did not affect the performance of systems needed to satisfy the objective of this test.
2.20 STP-34, OFFG AS PERFORMANCE VERIFICATION The objectives of this test is to verify that the Offgas System operates within the TS limits and expected operating conditions.
The new fuel design did not affect the performance of systems needed to satisfy the objective of this test.
2.21 STP-35, RECIRCULA flON SYSTEM FLOW CAllBRATION The objective of this test is to perform a complete calibration of the recirculation system flow I instrumentation, int.uding specific signals to the plant monitoring system. l The new fuel design did not affect the performance of systems needed to sati<y the objective of this test.
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- 3. Limerick Generating Station Unit 2 Startup Test Report Page 10 of 21 JBG:sja 2.22 STP-36, PIPING DYNAMIC TRANSIENTS The objectives of this test are to verify that the following piping systems are adequately designed and restrained to withstaad the following transient loading conditions:
1 Main Steam - Main Turbine Stop Valve / Control Valve closures at approximately 20-25%,60-80%, and 95-100% of rated thermal power.
Main Steam and Relief Valve Discharge - Main Steam Relief Valve actuation.
Recirculation - Recirculation Pump trips and restarts.
liPCI steam supply - 11PCI turbine trips.
Feedwater - Reactor feed pump trips /coastdowns.
The new fuel design did not affect the performance of systems needed to satisfy the objectives of this test.
2.23 STP 70, REACTOR WATER CLEANUP SYSTEM The objective of this test is to demonstrate specific aspects of the mechanical operability of the Reactor Water Cleanup System.
l The new fuel design did not affect the performance of systems needed to satisfy the objective of this test.
l 2.24 STP-71, RESIDUAL IIEAT REMOVAL SYSTEM l
The objective of this test is to demonstrate the ability of the Residual lieat Removal (RilR) System to i remove residual and decay heat from the nuclear system so that refueling and nuclear servicing can be performed. Additionally, this test will demonstrate the ability of the RiiR System to remove heat from the suppression pool.
l The new fuel design did not affect the performance of systems needed to satisfy the objective of this test.
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I Limerick Generating Station j Unit 2 Startup Test Report '
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i 3.0 UFSAR CHAPTER 14.2 TESTS REQUIRED 3.1 STP-1, CIIEMICAL AND RADIOCHEMICAL i The principal objectives of this test are (1) to secure information on the chemistry and radiochemistry of l the reactor coolant, and (2) to determine that the sampling equipment, procedures and analytical techniques l l are adequate to supply the data required to demonstrate that the chemistry of all parts of the entire reacto,
- system meet specifications and process requirements. !
I ACCEPTANCE CRITERI A l LevelI i
l l Chemical factors defined in the TS and fuel warranty must be maintained within the limits specified. The :
, activity of gaseous and liquid effluents must conform to license limitations. Water quality must be known .)
l at all times and must remain within the guidelines of the water quality specifications.
Level 2 !
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RESULTS During Startup of LGS Unit 2 reactor, following its fourth refueling outage, reactor coolant chemistry parameters as well as radioactive gaseous waste releases and radioactive liquid waste releases were maintained within the limits set forth in the LGS Unit 2 TS. The following is a list of Chemistry related surveillance tests (ST) satisfactorily performed in support of unit startup activities:
ST-5-041-800-2, ST-5-041-875-2, ST-5-041-876-2, ST-5-041-877-2, ST-5-041-878-2, ST-5-041-879-2, ST-5-041-885-2, ST-5-061-570-0, ST-5-070-885-2, ST-5-076-810-2, ST 5-076-815-2 l
In addition to the surveillance tests, routine tests and normal analyses were performed. Results are as follows:
PARAMETER ACTUAL DATA ACCEPTANCE (l00 %)3/7/97 CRITERIA i Primary Rx Coolant 2.28 x 10-4 50.2 pCi/gm )
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! Primary Rx Coolant .086 $1.0 1
! Conductivity Primary Rx Coolant 7.20 j>5.6 to 58.6 pil Primary Rx Coolant 0.25 5200 Chloride 510 ppb i
Fuel Warranty Appendix 1 - Water Quality Requirements were met during startup. On March 7,(first day past outage at approximately 100% power), feedwater copper concentration was 0.039 ppb, iron was 1.72 ppb and total metals was 2.0 ppb (fuel warranty limit 2 ppb,10 ppb, and 15 ppb re :pectively). Condensate demineralizer effluent conductivity was 0.058 pmho/cm.
Condensate and reactor water cleanup demineralizer performance was monitored closely during the startup.
Demineralizers were regenerated as necessary to maintain reactor water conductivity less than 0.3 pmho/cm.
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- Limerick Generating Station Unit 2 Startup Test Report Page 12 of 21 JBG:sja 3.2 STP-2, RADIATION MEASUREMENTS OBJECTIVES The objectives of this test are to (1) determine the background radiation levels in the plant environs prior to operation for base data to assess future activity buildup, and (2) monitor radiation at selected power levels to assure the protection of personnel and continuous compliance with the guideline standards of 10CFR20 during plant operation.
ACCEPTANCE CRITERI A' Level 1 l
The radiation doses of plant origin and the occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of the standards for protection against radiation as outlined in 10CFR20 " Standards for Protection Against Radiation."
Level 2 None RESULTS Radiation surveys were conducted at power level of 100% in accordance with GP-2 Appendix 6, Normal Plant Startup - Health Physics. Radiation shielding as described in the UFSAR was verified as adequate.
Radiation dose rates remained within the standards for protection against radiation outlined in 10CFR20 !
NRC General Design Criteria thus meeting test criteria.
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Limerick Generating Station Unit 2 Startup Test Report
! Page 13 of 21 JBG:sja 3.3 STP-3, FUEL LOADING l OBJECTIVE i
The objective of this test is to load fuel safely and efliciently to the full core size.
i ACCEPTANCE CRITERIA l Level 1 The core is fully loaded in accordance with established procedures, and the partially loaded core must be subcritical by at least 0.38% Ak/k with the analytically determined strongest rod fully withdrawn.
Level 2 l None i
i RESULTS The beginning of cycle shutdown margin calculated in the Cycle Management Report Limerick 2 Cycle 5 was 1.40% Ak/k. Core reload was conducted in accordance with Technical Specifications. Equipment i required to be operable to ensure that the shutdown margin is maintained wa; verified operable by various l performances of ST-6-107-630-2 and ST-6-107-591-2 between January 30,1997 and February 25,1997.
Post alteration core verification was ;ompleted on February 19,1997 after all refueling operations were l completed by the performance of M-C-797-020. All fuel bundles were verified to be in their proper core locations and properly oriented in the control cell. The bundle seating pass identified ten fuel bundles improperly seated (57-16,45-50,45-34,33-22,31-34,25-46,25-34,43-20,31-04,41-08). All were subsequently corrected.
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3.4 STP-4, SHUTDOWN MARGIN DEMONSTRATION OBJECTIVES The objective of this test is to demonstrate that the reactor will be sufficiently subcritical throughout the cycle with any single control rod fully withdrawn.
ACCEPTANCE CRITERIA )
l Level 1 1
The shutdown margin (SDM) of the fully loaded, cold (68 'F), xenon-free core occurring at the most l reactive time during the cycle must be at least 0.38% Ak/k with the analytically strongest rod (or its j l reactivity equivalent) withdrawn. If the SDM is measured at some time during the cycle other than the most reactive time, compliance with the above criteria is shown by demonstrating that the SDM is 0.38%
Ak/k plus an exposure dependent correction factor which corrects the SDM at that time to the minimum SDM. I l
Level 2 Criticality should occur within +/-l.0% Ak/k of the predicted critical.
RESULTS For Unit 2 Cycle 5, the required shutdown margin must be greater than 0.38% Ak/k where R is equal to 0.000% Ak/k. Therefore, the calculated shutdown margin for Cycle 5 must be greater than 0.38% Ak/k. l On February 26,1997 as Unit 2 reached criticality, data was collected to calculate shutdown margin in accordance with ST-3-107-870-2, shutdown n;argin determination. Cycle 5 shutdown margin was determined to be 1.421% Ak/k. This satisfies the Level 1 acceptance criteria.
The difference between the temperature corrected eigenvalue at criticality and the predicted critical eigenvalue was determined to be 0.021% Ak/k. This satisfies the level 2 acceptance criteria.
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- c e' - Limerick Generating Station Unit 2 Startup Test Report Page 15 of 21 JBG
- sja 3.5 STP-5, CONTROL ROD DRIVE SYSTEM OBJECTIVES The objectives of this test are (1) to demonstrate that the Control Rod Drive (CRD) System operates properly over the full range of primary coolant operating temperatures and pressures, and (2) to determine the initial operating characteristics of the CRD system.
ACCEPTANCE CRITERIA Level 1 Each CRD must have a normal withdrawal speed less than or equal to 3.6 inches per second, indicated by a full 12 foot stroke in greater than or equal to 40 seconds.
The mean SCRAM time of all operable CRD's must not exceed the following times (SCRAM time is measured from the time the pilot SCRAM valve solenoids are de-energized):
Position Inserted to From Fully Withdrawn SCRAM Time (Seconds) 45 0.43 39 0.86 25 1.93 05 3.49 The mean SCRAM time of the three fastest CRD's in a two by two array must not exceed the following times (SCRAM time is measured from the time the pilot SCRAM valve solenoids are de-energized):
Position Inserted to From Fully Withdrawn SCRAM Time (Seconds) 45 0.45 39 0.92 25 2.05 05 3.70 L.evel 2 Each CRD must have normal insert and withdrawal speeds of 3.0 + 0.6 inches per second, indicated by a full 12 foot stroke in 40 to 60 seconds.
RESULTS Although the performance of the CRD System was not affected by the installation of the new fuel design, the SCRAM time limits is required by TS to assure thermal limits, such as critical power ratio, are not exceeded. Therefore, level I tests were performed Level I stroke time acceptance criteria were fully satisfied by the performance of RT-6-047-760-2 from February 22 through March 1,1997 during the operational hydrostatic test and startup.
Level 1 SCRAM time acceptance criteria were fully satisfied by the performance of ST-3-107-790-2 from February 22 through March 4,1997 during the operational hydrostatic test and startup.
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3.6 STP-6, SRM PERFORMANCE AND CONTROL ROD SEQUENCE OBJECTIVES
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The objective of this test is to demonstrate that the operational neutron sources, Source Range Monitoring l (SRM) instrumentation, and control rod withdrawal sequences provide adequate information to achieve criticality and increase power in r safe and efficient manner.
l ACCEPTANCE CRITERI A Level 1 f
There must be a neutron signal to noise count ratio of a least 2:1 on the required operabia SRM. I There must be a minimum count rate of 3 counts /second (CPS) on the required operable SRM.
Level 2 l None RESULTS i
Minimum SRM count rate was detennined to be greater than 3 CPS by J. e performance of ST-6-107-590-2 l prior to the withdrawal of control rods on February 26,1997. The signa -to-e.'se ratio verification is only ;
required to be performed in accordance with TS if the SRM count rate is less than 3.0 CPS.
Since at no time during the startup was the count rate less than 3.0 CPS, this verification was not performed. SRM response was verified by the p:rformance of ST-3-107-870-2 on February 26,1997, until criticality was achieved.
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3.7 STP-10,IRM PERFORMANCE OBJECTIVES l
I The objective of this test is to adjust the Intermediate Range Monitoring (IRM) System to obtain an {
optimum overlap with the SRM and Average Power Range Monitor (APRM) systems.
ACCEPTANCE CRITERI A Level 1 1
Each IRM channel must be on scale before the SRM's exceed their rod block setpoint.
Each APRM must be on scale before the IRM's exceed their rod block setpoint.
t Level 2 Each IRM channel must be adjusted so that one-half decade overlap with the SRM's is assured.
l Each IRM channel must be adjusted so that one decade overlap with the APRM's is assured. !
RESUI TS j 1
TS SRM/lRM overlap was satisfied by the performance of ST-6-107-884-2 on February 26,1997. This I test demonstrated at least a half decade SRM/IRM overlap.
During startup, all required APRM's were verified to be on scale before any IRM exceeded their SCRAM setpoint of 120% of scale. This was documented on General Plant procedure GP-2,"Mormal Plant Startup," on February 27,1997. One-half decade of IRM/APRM overlap is verified in accordance with TS during each controlled shutdown by the performance of ST-6-107-886-2.
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j Unit 2 Startup Test Report l
l Page 18 of 21 l JBG:sja l
1 3.8 STP-11, LPRM CALIBRATION l
OBJECTIVES The objective of this test is to calibrate the Local Power Range Monitoring (LPRM) System.
! ACCEPTANCE CRITERIA l l
Level I None I
l Level 2 I
i Each LPRM reading will be within 10% ofits calculated value.
RESULTS LPR M calibration was performed at 100% power per ST-2-074-505-2 The LPRM's were calibrated to l l
within 10% of their calculated value.
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e' - Limerick Generating Station Unit 2 Startup Test Report j Page 19 of 21
, JBG:sja 3.9 STP-12, APRM CALIBRATION '
l l OBJECTIVES l
The objective of this test is to calibrate the APRM System.
l ACCEPTANCE CRITERI A 1
Level 1 The APRM channels must be calibrated to read equal to or greater than the actual core thermal power.
In the startup mode, all APRM channels must produce a SCRAM at less than or equal to 15% of rated thennal power.
Level 2 ,
1 if the above criteria are satisfied, then the APRM channels will be considered to be reading accurately if j they agree with the heat balance fraction of rated power to within (+2,-0)% of rated power.
RESULTS l
l By various perfonnances of ST-6-107-885-1, Level 1 acceptance criteria were met by verifying APRM l channels were indicating greater than or equal to actual core thermal power and below the SCRAM and j Rod Block setpoints when thennal power was greater than 25%. Level 2 acceptance criteria were also met in this ST by adjusting indicated APRM reading to within +2,-0% (not to exceed 100%) of the fraction of l
rated power.
l l The Level I acceptance criteria of APRM SCRAM setpoint of 15% was met by channel functional tests l ST-2-074-412-2, ST-2-074-413-2, ST-2-074-414-2, ST-2-074-415-2, ST-2-074-416-2, and )'
l ST-2-074-417 2 performed from January 5,1997 through January 10,1997.
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- *' Limerick Generating Station i Unit 2 Startup Test Report l j Pa;e 20 of 21 JBG:sja 3.10 STP-18, TIP UNCERTAINTY i i
OIUECTIVES The objective of this test is to determine the reproducibility of the Traversing incore Probe (TIP) system readings.
ACCEPTANCE CRITERI A I
Level 1 1 None i
Level 2 j i
The total TIP uncertainty (including random noise and geometrical uncertainties) obtained by averaging !
the uncertainties of all data sets shall be less than 7.1%. I RESULTS 1 l
l Total TIP uncertainty was determined by the performance of Routine Test procedure RT-3-074-850-0,
" Core Power Symmetry and TIP Reproducibility Test," on March 10,1997. Level 2 acceptance criteria were met by all data sets with a total uncertainty of 1.12%.
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! e' ' Limerick Generating Station Unit 2 Startup Test Report Page 21 of 21 JBG:sja l 3.11 STP-19, CORE PERFORMANCE I OBJFCTIVES l
The objectives of this test are to (1) evaluate the core thermal power and core flow rate, and (2) evaluate whether the core performance parameters are within limits.
ACCEPTANCE CRITERI A l Level I l l The following thermal limits are < l.000:
- 1. CMFLPD (Core Maximum Fraction of Limiting Power Density)
- 2. CMFCP (Core Maximum Fraction of Critical Power)
- 3. CMAPR (Core Maximum Average Planar Ratio)
Steady-state reactor power shall be limited to the rated core thermal power (.7458 MWt).
Core flow shall not exceed its rated value (110 Mlb/hr).
Level 2 None l
RESULTS j With thermal powe limited to 3458 MWth and core flow limited to 110 Mlbhr, Level 1 acceptance criteria of thermal limits were met and documented throughout the startup by various performances of ST-6-107-885-2 from February 28,1997 through March 2,1997. j I
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