NLS2013027, Reload 27, Cycle 28 Startup Report

Reload 27, Cycle 28 Startup Report

ML13056A448
Person / Time
Site:	Cooper
Issue date:	02/15/2013
From:	Vanderkamp D Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2013027
Download: ML13056A448 (17)

Text

H Nebraska Public Power District Always there when you need us NLS2013027 February 15, 2013 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Reload 27, Cycle 28 Startup Report Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46

Dear Sir or Madam:

The purpose of this letter is to inform you that the acceptance criteria for the startup tests described in Cooper Nuclear Station Updated Safety Analysis Report, Chapter XIII, Section 5.0, have been met for the recent Cycle 28 startup. The startup test program was completed on January 2, 2013. The attachment provides a summary of the results.

This letter makes no commitments. If you have any questions concerning this report, please contact me at (402) 825-2904.

Sincerely, David W. Van Der Kamp Licensing Manager

/lb

Attachment:

Startup Report - Reload 27, Cycle 28 cc: Regional Administrator w/attachment USNRC - Region IV Senior Project Manager w/attachment USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/attachment USNRC - CNS NPG Distribution w/o attachment Records w/attachment COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 wwwnppd.com

NLS2013027 Attachment Page 1 of 16 Startup Report - Reload 27, Cycle 28 Startup Report Introduction The following information is from the Cooper Nuclear Station (CNS) Updated Safety Analysis Report (USAR) Chapter XIII, Section 5.0 and is included for information.

"A summary report (StartupReport) ofplant startup and power escalationtesting is submitted following:...

3. Installationoffuel that has a different design or has been manufactured by a differentfuel supplier...

The Startup Report addresseseach of the tests identified in the USAR and includes a description of the measuredvalues of the operatingconditions or characteristicsobtainedduring the test program and a comparisonof these values with design predictionsand specifications.Any corrective actions that were requiredto obtain satisfactory operation is also described.Any additionalspecific details requiredin license conditions based on other commitments is included in this report.

A startup report is submitted within (1) 90 days following completion of the startup test program, (2) 90 days following commencement of commercialpower operation or subsequent resumption ofpower operation, or (3) 9 months after criticalityis reached,whichever is earliest.

Supplementary reports are submitted every 3 months until all three of these events are complete."

The CNS Cycle 28 reload core contains fuel of a different design than previously used; therefore, this startup report is being submitted under provision 3 of USAR XIII, Section 5.0.

The tests below are from the Startup and Test Program. The purpose, description, and criteria, when cited, are directly from the USAR. The summary of results contains either: a) the results of the test, or b) an explanation of why the test was not necessary for this startup testing, and/or, c) an explanation of differences in the current testing if appropriate.

Test Number 1 - Chemical and Radiochemical "Purpose The principalobjectives of this test are a) to maintain control of and knowledge about the quality of the reactorcoolant chemistry, and b) to determine that the sampling equipment,procedures, and analytic techniques are adequate to supply the data requiredto demonstrate that the coolant chemistry meets water quality specificationsand process requirements.

Secondary objectives of the test program include data to evaluate the performance of the fuel, operation of the demineralizersandfilters, condenser integrity, operation of the off-gas system, and calibrationof certainprocess instruments."

NLS2013027 Attachment Page 2 of 16 Summary of Results This test was not performed for this startup due to the established procedures in place regarding monitoring of water quality for Technical Specification and other program compliance.

Test Number 2 - Radiation Measurements "Purpose To determine the backgroundgamma and neutron radiationlevels in the plant environs priorto operationin orderto provide base data on activity buildup. Also to monitor radiationat selected power levels to assure the protection ofpersonnel and continuous compliance with the guideline standardsof JOCFR20 duringplant operation."

Summary of Results This test was not necessary for this startup due to the established procedures in place regarding monitoring of radiation.

Test Number 3 - Fuel Loading "Purpose The purpose of this test is to loadfuel safely and efficiently to the full core size."

Summary of Results This test and its requirements were written for initial core load. For this cycle, the core was loaded by shuffling the fuel with source range monitoring and shutdown margin calculations completed in accordance with established procedures written to comply with the existing Technical Specifications. These tests were therefore not necessary for this fuel loading.

Test Number 4 - Full Core Shutdown Margin "Purpose The purpose of this test is to demonstrate that the reactor will be subcriticalthroughoutthe first fuel cycle with any single control rodfully withdrawn.

Description This test will be performed in the fully loaded core at ambient temperaturein the Xenon-free condition. Subcriticalitywill be demonstrated with the strongest rodfully withdrawn and an adjacent rodpulled to a position calculatedto be equal to a shutdown margin specified to accountfor expected reactivity changes during core lifetime. This calculatedmargin also allows

NLS2013027 Attachment Page 3 of 16 for geometric and materialsasymmetries in the core plus a further allowancefor calculational and analyticalerrors.

Criteria Level 1

a. The fully loaded core must be subcriticalwith the strongest controlrodfully withdrawn and a shutdown margin > 0. 35% AK/K

b. If(a) cannot be satisfied, then the shutdown margin of the fully loaded core is satisfied if the reactor remains subcritical by > 0.25% AK/K during the sequential, complete withdrawal and insertionof every control rod within the core."

Summary of Results The test was performed prior to startup at 169°F and xenon-free. The test rod sequence was the normal startup rod withdrawal sequence. The strongest rod was not pulled; this was accounted for analytically. The calculated shutdown margin was 1.659% AK/K. This meets Criterion a.

Test Number 5 - Control Rod Drives "Purpose To demonstratethat the Control Rod Drive (CRD) System operatesproperly over the full range ofprimary coolant temperatures andpressuresfrom ambient to operating,andparticularlythat thermal expansion of core components does not bind or significantlyslow control rod movements. Also, to determine the initial operatingcharacteristicsof the entire CRD System."

Summary of Results These tests were not specifically performed for this startup as there was no impact of the fuel design change on the CRD system. The established procedures provide for normal withdrawal and insertion timing and compliance with current Technical Specification scram times.

Test Number 6 - SRM Response and Control Rod Sequence "Purpose The purpose of this test is to demonstrate that the operationalsources, SRM instrumentation,and rod withdrawal sequences provide adequate information to achieve criticalityand increase power in a safe and efficient manner. The effect of typical rod movements on reactorpower will be determined."

NLS2013027 Attachment Page 4 of 16 Summary of Results This test was not specifically performed for startup as the fuel design change did not affect the design or operational requirements of the Source Range Monitor (SRM) or Intermediate Range Monitor (IRM) systems. Established procedures comply with the Technical Specification requirements on signal-to-noise ratio, minimum count rate, and SRM/IRM overlap.

Test Number 9 - Water Level Measurement "Purpose To verify the calibrationand agreement of the GEMAC and YARWAY water level instrumentationunder various conditions."

Summary of Results This test was not specifically performed for startup as the fuel design change did not affect the design or operational requirements of the water level instrumentation. Established procedures comply with the Technical Specification requirements on the instrumentation.

Test Number 10 - IRM Performance "Purpose To adjust the IntermediateRange Monitor system to obtain an optimum overlap with the SRM and APRM systems."

Summary of Results This test was not specifically performed for startup as the fuel design change did not affect the design or operational requirements of the SRM, IRM, or Average Power Range Monitor (APRM) systems. Established procedures comply with the Technical Specification requirements on SRM/IRM and IRM/APRM overlap.

Test Number 11 - LPRM Calibration "Purpose To calibrate the Local Power Range Monitoring System.

Description The LPRM channels will be calibratedto make the LPRM readingsproportionalto average heat flux in the four cornerfuel rods surroundingeach chamber at the chamber elevation. The calibrationfactors are obtainedfrom either an off-line or process computer calculation.

NLS2013027 Attachment Page 5 of 16 Criteria Level 1 With the reactorin the rodpattern and at the power level at which the calibrationis to be performed, the meter readingof each LPRM chamber will be proportionalto the neutronflux in the narrow-narrowwatergap at the height of the chamber."

Summary of Results This test was performed at rated power and steady-state xenon conditions per existing plant procedures. The Local Power Range Monitors (LPRMs) were successfully calibrated as required by the plant Technical Specifications.

Test Number 12 - APRM Calibration "Purpose To present the methodfor calibratingthe Average Power Range Monitor System.

Description Each APRM channel reading will be adjusted to be consistent with the core thermalpower as determinedfrom the heat balance. Duringheatup a preliminarycalibrationwill be made by adjusting the APRM amplifier gains so that the APRM readings agree with the results of a constant heatup rate heat balance. The APRMs should be recalibratedin the power range by a heat balance as soon as adequatefeedwater indication is available.

Criteria Level I The APRM channels must be calibratedto read equal to or greaterthan the actualcore thermal power.

Technical Specification and Fuel WarrantyLimits on APRM scram and Rod Block shall not be exceeded.

In the startup mode, all APRM channels must produce a scram at <15% of rated thermalpower.

Recalibrationof the APRM System will not be necessaryfrom safety considerationsif at least two APRM channelsper RPS trip circuithave readingsgreater than or equal to core power.

Level 2 If the above criteriaare satisfiedthen the APRM channels will be considered to be reading accurately if they agree with the heat balance to within +/- 7% of ratedpower. "

NLS2013027 Attachment Page 6 of 16 Summary of Results This test was performed using the established calibration procedures. Established procedures comply with the Technical Specification requirements on APRM operation and these were successfully performed.

Test Number 13 - Process Computer "Purpose To verify the performance of the process computer under operatingconditions.

Description GE/PA C computer system programverifications and calculationalprogram validationsat static and at simulateddynamic input conditions will be preoperationallytested at the computer supplier's site andfollowing delivery to the plant site. Followingfuel loading, duringplant heatup and the ascension to ratedpower, the nuclear steam supply system and the balance-of-plant system process variablessensed by the computer as digital or analogsignals will become available. Verify that the computer is receiving correct values of sensed process variables and that the results ofperformance calculationsof the nuclearsteam supply system and the balance-of-plant are correct. Verify proper operation of all computerfunctions at ratedpower operating conditions.

Criteria Level 2 Program OD-1 and P-1 will be consideredoperationalwhen 1) the MCHFR calculated by an independent method and the process computer either a) are in the same fuel assembly and do not differ in value by more than 10%, or b) if two differentfuel assemblies are chosen by the two methods, the CHFR calculated by the other method in each assembly agrees with the MCHFR in that assembly by not more than 10%, and 2) when the LPRM calibrationfactors calculatedby the independent method and the process computer agree to within 5%.

The remainingprograms will be consideredoperationalupon successful completion of static testing and dynamic testing.

Summary of Results This test was not performed as written due to changes in the plant process computer system since the initial startup test program. The OD-1 and thermal limits programs in the current computer system were successfully used during startup and LPRM calibration using established plant procedures.

NLS2013027 Attachment Page 7 of 16 Test Number 14 - RCIC System "Purpose To verify the operationof the Reactor Core Isolation Cooling (RCIC)system over its expected operatingpressurerange."

Summary of Results This test was not performed specifically for this startup as the fuel design changes did not impact the RCIC system.

Test Number 15 - HPCI System "Purpose The purpose of this test is to verify the proper operation of the High Pressure Coolant Injection (HPCI)system over its expected operatingrange."

Summary of Results This test was not performed specifically for this startup as the fuel design changes did not impact the HPCI system.

Test Number 16 - Selected Process Temperatures "Purpose The purposes of this test are a) to establish the minimum reactorrecirculationpump speed which will maintainwater temperature in the bottom head of the reactor vessel within 145°F of reactor coolant saturationtemperature as determined by reactorpressure, and b) to provide assurance that the measuredbottom head drain temperaturecorresponds to bottom head coolant temperature during normal operations."

Summary of Results This test was not performed specifically for this startup as there was not an impact on the physical configuration of the reactor recirculation system or its ability to mix the reactor coolant adequately.

Test Number 17 - System Expansion "Purpose To verify that the reactordrywell piping system isfree and unrestrainedin regardto thermal expansion and that suspension components arefunctioning in the specified manner. The test also provides datafor calculationof stress levels in nozzles and weldments. "

NLS2013027 Attachment Page 8 of 16 Summary of Results This test was not performed as the changes made did not impact the physical configuration of the reactor drywell piping system.

Test Number 18 - Core Power Distribution "Purpose To 1) confirm the reproducibilityof the TIP system readings, 2) to determine the core power distributionin three dimensions, and 3) to determine core power symmetry.

Description Core power distribution includingpower symmetry will be obtained during the power ascension program. Axial power traces will be obtained at each of the TIP locations. Several TIP systems have been provided to obtain these traces; a common location can be traversedby each TIP chamber to permit intercalibration.

A check of the reproducibilityof the TIP traces is made at least twice; once near thefirst time the TIP system is used, and again after the TIP system has been used several times. The check is made with the plant at steady-state conditions by producingseveral TIP traces in the same location with each TIP machine. Tracesfrom the same TIP machine are evaluated to determine the extent of deviations between them. The results of the complete set of TIP traces may also be evaluated to determine core power symmetry.

Criteria Level 2 In the TIP reproducibilitytest, the TIP traces shall be reproduciblewithin +/- 3.5% relative error or + 0. 15 inch absolute errorat each axialposition (whichever is greater) in the non-boiling region."

Summary of Results The Traversing Incore Probe (TIP) reproducibility section of this test was not performed as the fuel design change did not require a change in TIP detectors or TIP system operation. The core power distribution and core power symmetry were evaluated successfully by the OD- I and plant computer programs as part of the LPRM calibration.

NLS2013027 Attachment Page 9 of 16 Test Number 19 - Core Performance "Purpose To evaluate the coreperformanceparametersof the coreflow rate, core thermalpower level, maximum fuel rod surface heatflux, core minimum criticalheatflux ratio (MCHFR), maximum averageplanarheatflux, and core minimum bundle power ratio (MBPR).

Description Core power level, maximum heatflux, recirculationflow rate, hot channel coolantflow, minimum criticalheatflux ratio,fuel assembly power, and steam qualitieswill be determined at existing power levels. Plant and in-core instrumentation,conventional heat balance techniques and core performance worksheets, and monograms will be used. This will be performed above 10% power and at variouspumping conditions and can be done independently of the process computerfunctions.

Level 1 The maximum fuel rod heatflux during steady-state conditions shall not exceed allowable heat flux. The design allowable heatflux is 135 W/cm 2 .

MCHFR shall be maintainedat or above the flow dependent limit line which passes through a MCHFR limit of 1.9forfull power andfullflow.

Steady-state reactorpower shall be limited to values on or below the licensedflow control line (Maximum power of 2,381 MWt with coreflow of at least 73.5 x 106 lbs/hr.)

The minimum bundle power ratio (MBPR) shall not be maintainedgreaterthan or equal to 1.0.

The maximum averageplanarlinearheat generationrate (MAPLHGR) shall not exceed the Technical Specification limits."

Summary of Results The fuel rod heat flux, MCHFR, and MBPR are no longer parameters of interest. The current thermal limit values (Maximum Fraction of Limiting Critical Power Ratio - MFLCPR, Maximum Average Planar [Linear Heat Generation Rate] Ratio [to the limit] - MAPRAT, and Maximum Fraction of Limiting Power Density - MFLPD) have all been maintained less than the limits allowed in Technical Specifications. Steady-state reactor power (licensed 2,419 MWth) with core flow (licensed 77.175 Mlb/hr) is limited to values on or below the licensed flow control line of 118.9%.

NLS2013027 Attachment Page 10 of 16 Test Number 20 - Steam Production "Purpose To demonstrate that the reactorsteam production warranty rate is satisfied."

Summary of Results This test applied only to initial plant operation and was not performed for this startup.

Test Number 21 - Flux Response to Rods "Purpose The purpose of this test is to demonstrate the stability of the core power reactivityfeedback mechanism with regardto small perturbationsin reactivity caused by rod movement.

Description Rod movement tests will be made at chosen power levels to prove that the transientresponse of the reactorto a reactivityperturbationis sufficiently stable over the full range of reactorpower andflow conditions. The signalfrom a nearby LPRM string will be measuredand evaluated to determine the local core dynamic effects of the rod movement.

Criteria Level 1 The decay ratio must be less than 1. Ofor each process variable that exhibits oscillatory response to control rod movement.

Level 2 The decay ratio is expected to be less than or equal to 0.25 for each process variable that exhibits oscillatoryresponse to control rod movement when the plant is operatingabove the lower limit setting of the Master Flow Controller."

Summary of Results This test was not performed as written as the Master Flow Controller is not used. LPRM response to adjacent control rod withdrawal was examined and the LPRMs behaved as expected.

NLS2013027 Attachment Page 11 of 16 Test Number 22 - Pressure Regulator "Purpose The purposes of this test are 1) to determine the optimum settingsfor the pressure control loop by analysis of the transientsinduced in the reactorpressure control system by means of the pressureregulators,2) to demonstrate the takeover capability of the backup pressure regulator upon failure of the controllingpressure regulatorand to set spacing between the set points at an appropriatevalue and 3) to demonstrate smooth pressurecontrol transitionbetween the governor valves and bypass valves when reactorsteam generation exceeds steam used by the turbine."

Summary of Results This test was not performed as no changes were made that would affect the pressure regulator.

Regulator settings are controlled by established plant procedures.

Test Number 23 - Feedwater System "Purpose The purposes of this test are 1) to adjust the feedwater controlsystem for acceptable reactor water level control, 2) to demonstrate stable reactor response to subcooling changes, 3) to demonstrate the capability of the automatic coreflow runbackfeature to prevent low water level scramfollowing the trip of one feedwater pump and 4) to demonstrate adequate response to feed heater loss."

Summary of Results This test was not performed as the feedwater control system was not modified by the fuel design change.

Test Number 24 - Bypass Valves "Purpose To demonstrate the ability of the pressureregulatorto minimize the reactor disturbanceduring an abruptchange in reactor steam flow and to demonstrate that a bypass valve can be testedfor properfunctioning at ratedpower without causinga high flux scram."

Summary of Results This test was not performed as the turbine bypass system was not modified by these changes.

NLS2013027 Attachment Page 12 of 16 Test Number 25 - Main Steam Isolation Valves "Purpose To a) functionally check the main steam line isolation valves (MSIV)for proper operation at selectedpower levels, b) to determine reactortransientbehavior during andfollowing simultaneousfidl closure ofall MSIV andfollowing closure of one valve, and c) to determine isolation valve closure time."

Summary of Results This test was not performed as this change did not impact the MSIVs or main steam lines.

Test Number 26 - Relief Valves "Purpose To verify the proper operationof the dual purpose reliefsafety valves, to determine their capacity and response characteristics,and to verify their proper reseatingfollowing operation."

Summary of Results This test was not performed as the relief valves were not modified by these changes.

Test Number 27 - Turbine Stop and Control Valve Trips "Purvose To demonstrate the response of the reactorand its control systems to protective trips in the turbine andgenerator."

Summary of Results This test was not performed as the turbine stop and control valves were not modified by these changes.

Test Number 28 - Shutdown from Outside the Control Room "Purpose The purpose of this test is to demonstrate that the reactor can be broughtfrom a normal initial steady-statepower level to the point where cooldown is initiatedand under control with reactor vessel pressureand water level controlledfrom outside the control room."

Summary of Results This test was not performed as alternate shutdown panels were not modified by these changes.

NLS2013027 Attachment Page 13 of 16 Test Number 29 - Flow Control "Purpose To determine the plant response to changes in recirculationflow and thereby adjust the local control loops. Also to examine the plant overall loadfollowing capabilityin order to establish correct interfacing of the pressureandflow control systems includingfinal settingsfor the master and localflow controllers."

Summary of Results This test was not performed as the fuel design change did not require physical modification of the existing recirculation flow control system. In addition, load following is not used at CNS.

Test Number 30 - Recirculation System "Purpose The purposes of this test are a) to evaluate the recirculationflow andpower level transients following trips of one or both of the recirculationpumps, b) to obtain recirculationsystem performancedata, and c) to verify that no recirculationsystem cavitation will occur on the operable region of the power-flow map."

Summary of Results Minimum critical power ratio (MCPR) is analytically determined for both single and dual loop operation. The recirculation system was not physically modified for the fuel design change. The recirculation pump runback to 20% speed was not changed as a result of the fuel design change.

The cavitation region of the power/flow map continues to be off-limits for plant operation.

Test Number 31 - Loss of Turbine-Generator and Offsite Power "Purpose The purpose of this test is to determine the reactortransientperformance during the loss of the main generatorand all offsite power, and to demonstrate the correctperformance of the station electricity supply system."

Summary of Results This test was not performed as the generator and electrical systems were not physically modified due to the fuel design change.

NLS2013027 Attachment Page 14 of 16 Test Number 32 - Recirculation M-G Set Speed Control "Purpose The purpose of this test is to determine the individualizedcharacteristicsof the recirculation controlsystem (i.e., Drive Motor, Fluid Coupler, Generator,Drive Pump, and Jet Pumps), and to obtain acceptable speed control system performance by the adjustment of linearand nonlinear controllerelements."

Summary of Results This test was not performed as the recirculation system was not physically modified by the fuel design change.

Test Number 33 - Main Turbine Stop Valve Surveillance Test "Purpose The purpose of this test is to demonstrate an acceptableprocedurefor weekly turbine stop valve surveillance tests at a power level as high as possible without producing reactorscram."

Summary of Results This test was applicable only for initial plant startup and so was not performed.

Test Number 34 - Vibration Measurements "Purpose To obtain vibration measurements on various reactor components to demonstrate the mechanical integrity of the system to flow induced vibration and to verify the accuracy of the analytical vibration model. Testing is in response to AEC Safety Guide 20."

Summary of Results This test was applicable only for initial plant startup and so was not performed.

Test Number 35 - Recirculation System Flow Calibration "Purpose The purpose of this test is to perform a complete calibrationof the installed recirculationsystem flow instrumentation.

NLS2013027 Attachment Page 15 of 16 Description During the testingprogram at operatingconditions which allow the recirculationpumps to be operatedat the speeds requiredfor ratedflow at ratedpower, the jet pumpflow instrumentation will be adjusted to provide correctflow indicationbased on the jet pump flow. After the relationshipbetween drive flow and coreflow is established,the flow biasedAPRM/RBM system will be adjusted to match this relationship.

Criteria Level 1 Not applicable.

Level 2 Jetpump flow instrumentationshall be adjusted such that thejet pump totalflow recorderwill provide a correct coreflow indicationat rated conditions.

The APRM/RBM flow-bias instrumentationshall be adjusted to function properly at rated conditions."

Summary of Results This test was performed using a procedure to determine actual core flow and adjust instrumentation appropriately. The procedure was successfully performed.

Test Number 70 - Reactor Water Cleanup System "Purpose The purpose of this test is to demonstrate specific aspects of the mechanical operabilityof the Reactor Water Cleanup System. (This test, performed at ratedreactorpressure and temperature, is actually the completion of the preoperationaltesting that could not be done without nuclear heating)."

Summary of Results This test was not performed as the Reactor Water Cleanup system was not modified for this fuel design change.

NLS2013027 Attachment Page 16 of 16 Test Number 71 - Residual Heat Removal System "Purpose The purpose of this test is to demonstrate the ability of the Residual Heat Removal (RHR) System to remove residualand decay heatfrom the nuclearsystem so that refueling and nuclear system servicing can be performed and to condense steam while the reactor is isolatedfrom the main condenser."

Summary of Results This test of RHR system was not performed as the system was not modified for this fuel design change.

Test Number 72 - Drywell Atmosphere Cooling System "Purpose The purpose of this test is to verify the ability of the Drywell Atmosphere Cooling System to maintaindesign conditions in the drywell during operatingconditions and scram conditions."

Summary of Results This test was not performed as the drywell atmosphere cooling system was not modified for this fuel design change.

Test Number 73 - Cooling Water Systems "Purpose To verify that the performance of the Reactor Building Closed Cooling Water (RBCCW), Turbine Building Closed Cooling Water (TBCCW), and Service Water Systems are adequate with the reactorat ratedtemperature.

Summary of Results This test was not performed as the cooling systems were not modified for this fuel design change.