ML20198T313
| ML20198T313 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/07/1997 |
| From: | Helme R, Poteate B, Steckel R CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20198T294 | List: |
| References | |
| NUDOCS 9801270028 | |
| Download: ML20198T313 (28) | |
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l ENCLOSURE 2 l
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HRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 l DOCKET NO. 50-324/L1 CENSE NOS. DPR-62 l CYCLE 13 STARTUP REPORT I
t BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 POWER UPRATE STARTUP TEST REPORT FOR CYCLE 13
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HRUNSWICK STEAM EI.ECTRIC PLANT .
UNIT 2 POWER UPRATE STARTUP TEST REPORT !
FOR CYCLE 13
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Prepared by: / b N'T'"
@ RogerSteckel
, i frf/A/T //f0/'f7 Reviewed by: ~ Blair P'otente ' / '
Approved b ^ %
/ 7 Rots:1 E. llelme Power Uprate Project Manager
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-I Brunswick Steam Electric Plant - Unit 2. !
L Power Uprate Startup Test Report i For !
i Cycle 13 l
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Table of Contents .
StElk!Il fEt [
-1.0 E x ec u ti ve S u m mary. . .. . ......... . . . .. ... ...... . ..... . . ..... . .. ...... .. . .. . . ... ... . . . .. . .. . . . .... .. 1 :
2.0 Purpose................................................................................................... _2 3.0 Prog ram De sc ri ption . . . . . . . .. . . . .. . ... ...... .. . .. .. .... . . . .. . . .... . .. .. .... . . . .. .. . . . ... . . ... . ... . . 2 i
4.0- A ccept an ce Cri t eria.. . . .... . . . . .. .. . . ... .. ... ..... . . . . .. .. . . .. . . .. . . . ... . .. .. . . ... . . . . . . .. . .. . .. .. .. 3 !
5.0 Power Uprate Startup Test Program Summary......................................... 3 r
6.0 Te s t i n g R eq u i re me n t s . . . . . . .. . . . . . .. . ... . . .. . . ... . . .. .... . .. ...... .... . .. . . . .. . .. . .. . .. .. . . . . . .. . . 3. .
6.1 UFSAR Chapter 14 Tests Not Required for Power Uprate............ 5 6.2 UFS AR Chapter 14 Tests Required for Power Uprate................... 10 6.3 OtherTests...................................................................................... 21 6.4 License Cond i tion Te sting.............................................................. 21 IBhlt!!
! Unit 2 U FS AR Chapter 14 Tests............................................................... 23 ,
2 Te st Co n d i t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ... . . .25 3 Test s Pe rformed for Powe r Uprate............................................ ................ 26
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l Hrunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Pace 1 1.0 EXECUTIVE
SUMMARY
The Brunswick Unit 2 Power Uprate Startup Test Report is submitted to the Nuclear Regulatory Commission (NRC)in accordance with Unit 2 Technical Specifications. The report summarizes the startup testing performed on Unit 2 following implementation of power uprate during the thirteenth refueling outage. Power Uprate was implemented in accrrdance with Amendment No. 214 of Facility Operating License No. DPR 62.
The result of Power Uprate is an increase in reactor thermal power equal to 5% of the <
original rated thermal power. Testing specified in Chapter 14 of the UFSAR was addressed and evaluated for applicability to this increased licensed power rating.
The Reactor Mode Switch was placed in the Startup position on October 13,1997. The final synchronization to the grid was performed on Oce ber 21, marking the official end to the Unit 2 refueling outage. The new 100% power <as first achieved on October 26, 1997. All required power uprate startup tests were completed by November 4,1997. To successfully achieve the uprated power level, nine Special Procedures (SPs) were written and implemented in combination with various Surveillance Test procedures described in this report. No unusual online adjustments were required for the following plant systems:
Electro-llydraulic Contiol (EllC) - Pressure Regulation, Feedwater, Reactor Core isolation Cooling (RCIC), and liigh Pressure Coolant Injection (llPCI). All systems performed in a stable manner during both plant startup and transient testing. The unit is operating satisfactorily at power uprated conditions.
Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 2 2.0 PURPOSE The Brunswick Unit 2 Power Uprate Startup Test Report summarizes the testing performed on Unit 2 folloiving the implementation of power uprate which resulted in an increase in scactor thermal power equal to 5% of the original rated thermal power. Each test performed for power uprate is described in Section 6.0. This report is submitted in accordance with the requirements of the Unit 2 Technical Specincations.
3.0 PROGRAM DESCRIPTION The power uprate startup testing requirements were developed primarily from the review of the Unit 2 Technical Specifications, Chapter 14 of the UFSAR (Table 1), the General Electric (GE) Power Uprate Safety Analysis Report for the Brtmswick Steam Electric Plant Units 1 and 2, and the GE Uprate Test Prograrn Recommendations. The testing was conducted following the Unit 2 Thirteenth refueling outage. The results of this testing verified the unit's ability to operate at the uprated power level. Where possible, testing took credit for existing surveillance procedures.
The majority of testing falls within the following categories:
- 1. VeriDeation of the control systems (i.e., Feedwater and EllC-Pressure Regulation) are stable at power uprate conditions.
- 2. Verification of the high pressure injection systems (i.e., RCIC and HPCI) operate acceptably at uprated conditions.
- 3. Collection of data for comparison to original plant rated conditions.
Table 2 presents the Test Conditions at which startup testing was performed. Reactor core flow could be any Cow within the safe operating region of the power /How map that will produce the required powu level. Testing at a given Test Condition was completed prior to proceeding to the subsequent Test Condition. Prior to increasing power above the original rated thermal power level of 2436 MW , the Director of Site Operations' approval was required. Additional hold points were established at 97% and 100% of the new rated thermal power level of 2558 MWt. These hold points also required the approval of the Director el Site Operations.
Umnswick Steam Electric Plant - Unit 2 ;
Power Uprate Startup Test Report for Cycle 13 Pace 3 l
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l 4.0 ACCEP'1'?.NCE CRITERI A l l
Acceptance Criteria for Power Uprate testing are contained in the individual procedures used to perform the startup tests.
Level 1 Criteria: The values of process variables in the design of the plant and equipment are included in this category. If a Level I criterion is not satisfied, the plant will be placed in a satisfactory hold condition, until a resolution is made.
5.0 POWER UPRATE STARTUP TEST PROGRAM SUMMA RY The test prograrn began when the Mode Switch was placed in Startup on October 13, 1997 and ended with all required Power Uprate Startup Tests completed on November 4, 1997. The unit was synchronized to the grid on October 21,1997, marking the official end to the Unit 2 thirteenth refueling outage. The new uprated 100% power (2558MWt) was first achieved on October 26,1997.
The unit is operating satisfactorily at the uprated conditions. No unanticipated online adjustments were required to control systems for the following: EllC-Pressure Regulation, Feedwater, RCIC, or llPCI Systems. All systems performed in a stable manner.
Data collected at uprated conditions showed that the 5% increase in reactor power has little, if any, effect on reactor water chemistry or radiological conditions throughout the plant.
All Power Uprate Startup Tests were performed satisfactorily during startup from the thirteenth refueling outage. Table 3 identified all the UFSAR Chapter 14 required Power Uprate startup tests and the Test Conditions in which each test was performed. No Level I test failures occurred.
6.0 TFSTING REQUIREMENTS Each of the tests discussed in UFSAR Chapter 14, Section 14.2 was evaluated for applicability to Power Uprate. Throughout the following discussion, the test numbers, titles, and format are consistent with the UFSAR.
Section 6.1 identifies each Chapter 14 test not required to be performed for Power Uprate.
l The purpose of the test and rationale for exempting the test from the Power Uprate program are discussed.
l Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 4 i
Section 6.2 identifies each test required to be perfonned for Power Uprate. The purpose of the test, a description of the test, and the test results are included.
Table 1 identifies all the Chapter 14 tests and their applicability to power Uprate. Table 2 lists the five Test Conditions and the associated uprated power level. Table 3 lists the Chapter 14 tests performed for Power Uprate and the Test Condition (s) for each test. '
Note that many surveillance tests similar to the original Chapter 14 UFSAR tests are performed periodically, often during each startup. Therefore, the Power Uprate Test Program took credit for many existing plant procedures.
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Drunswick Steam Electric Plant Unit 2 Power Uprate Startup Test Report for Cycle 13 Page5 6.1 UFSAR Chapter 14 Table 14.2.1 1 Tests Not Required for Power Uprate.
6.1.1 Test 3 Fuel Loading This test demonstrates the ability to safely and efficiently load fuel. Fuel loading is an activity perfortned during refuel outages in accordance with site procedurca and Power Uprate has no affect on the evolution; therefore, no testing is required for Power Uprate.
6.1.2 Test 4 Full Core Shutdown Marghi The purpose of the Shutdown Margin test is to demonstrate that throughout the fuel cycle the reactor will be suberitical with the analytically deterrnined highest worth control rod being fully withdrawn with all other rods fully inserted. Power Uprate has no affect on core loading; therefore, no testing is required for Power Uprate. Ilowever, Shutdown Margin Demonstrations are required during a startup following core alterations and results are included in the Brunswick Unit 2, Cycle 13 Neutronics Startup Report.
6.1.3 Test 6 SRM Performance and Control Rod Sequence The purpose of this test is to demonstrate that the Source Range Monitor (SRM) instrumentation, and rod withdrawal sequences provide adequate information to the operator during startup. Power Uprate has no affect on the SRMs or Control Rod Sequence; therefore, no testing is required for Power Uprate. Monitoring of SRMs and Control Rod Sequence is a requirement of a normal startup sequence and is controlled independent of Power Uprate testing.
6.1.4 Test 7 IRM Performance The puqmse of this test is to demonstrate the ability to obtain optimum overlap between Intermediate Range Monitors (IRMs), SRMs and Average Power Range Monitors (APRMs). Power Uprate has no affect on IRMs; therefore, no testing is required for Power Uprate. Monitoring of the overlap is a requirement of a normal startup sequence and is controlled independent of Power Uprate testing.
6.1.5 Test 13 Selected Process Temperatures The purpose of this test is to establish the minimum reactor recirculation pump speed which would maintain water temperature in the bottom head of the reactor vessel within a
! specified tolerance of reactor coolant saturation temperature as determined by reactor j pressure and to provide assurance that the measured bottom head drain temperature corresponds to bottom head coolant temperature during normal operations. Temperature stratification limits are defined in the Technical Specifications and controlled by plant
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i Ilrunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 6 procednics during startup independent of Power Uprate stanup testing.
6.1.6 Test 14 System Expansion The purpose of this test is to verify reactor drywell piping and major equipment are unrestrained with regard to thermal expansion. An analysis for Power Uprate conditions indicates ti.e piping systems are acceptable for Power Uprate; therefore, no testing is required.
6.1.7 Test 15 Core Power Distribution The purpose of this test is to confirm the reproducibility of the computer stored Traversing incore Probe (TIP) system segment averaged values, to determine the core power distribution in three dimensions, and to determine core power symmetry. Existing plant procedures verify proper TIP operation and core power symmetry, Power Uprate will not significantly impact these parameters and will not affect the TIP system; therefore, no testing is required.
6.1.8 Test 18 Flux Response to Rods The purpose of this test is to demonstrate stability in the power-reactivity feedback loop with increasing reactor power and to determine the effect of control rod movement on reactor stability. Power Uprate has not changed the core design and the response of flux to the movement of control rods; therefore, no testing is required.
6.1.9 Test 20 Feedwater System The purpose of this series of tests is to demonstrate acceptable reactor water level control, to evaluate and adjust feedwater controls, to demonstrate the capability of the automatic flow run back feature to prevent a low water level scram following trip on one feedwater pump, to demonstrate adequate response to feedwater heater loss, and to demonstrate general reactor response to inlet subcooling changes. Of there tests, all are being excluded from the Power Uprate Startup Test Plan except for adjustment of feedwater controls. The loss of feedwater heating performed during initial startup demonstrates adequate response and further testing is not required.
Ilrunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 7 6.1.10 Test 22 Main Steam isolation Valves The purpose of this test is to functionally check MSIVs for proper operation at selected power levels, to determine reactor transient behavior during and following simultaneous full closure of all MSIVs and following closure of one valve, and to determine isolation valve closure time. Large transient testing performed at high power during the initial startup demonstrated the adequacy of protection. Analysis shows that should these transients occur at Power Uprate conditions, the change in unit performance will be small. MSIVs will continue to be tested by plant procedures during normal operation; therefore, further testing is not required.
6.1.11 Test 23 Relief Valves The purpose of this test is to verify proper operation of the dual pur;me safety relief valves (SRV), to detennine their capacity, and to verify proper rescating following operation. Power Uprate wal affect the SRVs by raising the lift set point by 25 psi per valve, and change the allowable as found tolerance from ( +/-) 1% to ( +/- ) 3%. Prior to the refuel outage, the SRVs were bench tested by the vendor, and satisfactorily tested by plant procedures during the reactor startup; therefore, they will not be included in the Power Uprate Startup Test Plan.
6.1.12 Test 24/25 Turbine Stop Valve Trip / Generator Load Rejection The purpose of the Turbine Stop Valve trip is to det nnine the response of the reactor to a fast closure of tmbine-generator stop valves and to. valuate the response of bypass valves, relief valves, and reactor protection system. The purpose of the Generator Load Reject test is to demonstnee the ability of the unit to reject design load without trip and to demonstrate scactor response is within expected limits. Large transient testing performed at high power during the initial startup demonstrated the adequacy of protection.
Analysis shows that should these transients occur at Power Uprate conditions, the change in unit perfonnance will be small; therefore, further testing is not required.
6.1.13 Test 26 Flow Control The purpose of this test is to determine plant response to changes on recirculation flow, and thereby, adjust the local control loops. Also, the load following capability of the plant is established. Power Uprate does not significantly affect the recirculation flow control system, or core flow limits; therefore, the recirculation flow control test is not required for Power Uprate Startup testing.
6.1.14 Test 27 Recirculation System The purpose of this test is to determine transient response and steady state conditions
Hrunswick Steam Electric Plant Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 8 ,
following recirculation pump trips and to obtain jet pump performance data, initial startup testing determined transient response of the recirculation system. Power Uprate did not affect the ability of the recirculation system to respond acceptably to these transients; therefore, recirculation system testing, as defined by this test,is not required for Power Uprate testing.
6.1.15 Test 28 Loss of Turbine Generator and Offsite Power The purpose of this test is to demonstrate proper performance of th: reactor and the plant electrical equipment and systems during a loss of auxiliary power transient. Power Uprate does not affect the ability of the electrical systems to function properly during a loss of the main turbine generator and a loss of offsite power; therefore, further testing is not required.
6.1.16 Test 29 Recirculation MG Set Speed Control The purpose cithis test is to determine the as-built characteristics of the recirculation control system. Power Uprate does not affect the recirculation flow loop and is therefore not included in the Power Uprate Startup Test Plan.
6.1.17 Test 30 Vibration Monitoring The pu pose of this test is to determine vibration characteristics of the reactor internals.
A comprehensive review was performed by GE for the affects of increase power and pressure conditions on the reactor vesselinternals. This review showed nontinued compliance with the original design following Power Uprate. Based on this analysis this test is not included in the Power Uprate Startup Test Plan.
6.1.18 Test 31 Shutdown From Outside the Control Room The purpose of this test is to demonstrate the ability to shutdown the plant to hot standby conditions from outside the control room. Power Uprate did not alter the ability of the reactor to be shutdow n from outside the control room; therefore, this test was not added to the Power Uprate Stanup Test Plan.
Ilrunswick Steam Electric Plant Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 9 6.1.19 Test 32 Residuallleat Removal (RilR) System i The purpose of this test is to demonstrate the ability of the RilR system to remove residual and decay heat from the nuclear system so that refueling and servicing can be performed and to condense steam while the reactor is isolated from the main condenser.
The capability of the RilR system to remove residual and decay heat has been demonstrated many times over the years. Power Uprate's effect on system performance is a small increase in the reactor cooldown time; therefore, the system will continue to perform acceptably and no further ter. ting is necessary. The steam condensing mode has been removed and thus, is not a factor. Therefore, this test was not added to the Power Uprate Startup Test Plan.
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Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 10 6.2 UFS AR Chapter 14, Table 14.2.1 1 Tests Required for Power Uprate 6.2.1 Test 1 Chemical and Radiochemical Purame:
The purpose of this test is to maintain control and knowledge of the quality of feedwater and reactor coolant chemistry. With Unit 2 increasing rated thermal power to 2558 MWt, it is desirable to track chemistry parameters and evaluate the results for uprated power.
Description:
Chemical and radiochemical samples were taken in accordance with plant procedures in Test Conditions 3,4, and 5.
Acceptance Criteria:
All acceptance criteria are established in procedure OAl 81," Water Chemistry ;
Guidelines".
Results:
Procedure OAl - 81 was performed satisfactorily in Test Conditions 3,4 and 5. All acceptance criteria was met.
Chemistry Results Parameter Test Condition 3 Test Condition 4 Test Condition 5 Cond .ctivity 0.095 0.084 0.084 (pmho/cm)
Dose Equivalent 5.55E 4 5.49E-4 4.64E-4 I 131 (pCi/mL) 6.2.2 Test 2 Radiation Measurements
Purpose:
The puipose of this test is to measure radiation levels at selected locations and power levels to ensure compliance with to CFR 20 during plant operations.
Ikscription:
Radiation levels were measured at various locations in the plant at uprated power levels
'during Test Conditions 4 and 5.
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Hrunswick Steam Electric plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 11 Acceptance Criterlat Level I : Radiation doses of plant origin and occupancy times of personnel in radiation zones are controlled consistent with the guidance on standards for protection against radiation found in 10 CFR 20.
1 Results:
Radiation surveys were conducted at uprated power levels in Test Conditions 4 and 5.
No postings were required to be changed as a result of achieving the uprated 100% power level. Radiation dose rates remain within the standards for protection against radiation outlined in 10 CFR 20.
6.2.3 Test 5 Control Rod Drive
Purpose:
The purpose of this test is to demonstrate that the Control Rod Drive (CRD) system- -.
operates properly over the full range of primaiy coolant temperatures and pressures. This
, test was included in the Power Uprate Startup to monitor system parameters at Power Uprate conditions. Verification of adequate cooling water and drive water flow was established as a license condition for approval of the Power Uprate license amendment.
Description:
Adequate cooling water flow and drive water flow was verified while operating in Test Conditions 4 and 5.
Acceptance Criteria:
All acceptance criteria are established in procedure 2SP-97-204," Unit 2 Power Uprate Data Collection".
Results:
All cooling water flow and drive water flow data taken from this test was found acceptable, r
6.2.4 Test 8 Local Power Range Monitor (LPRht) Calibration
Purpose:
The purpose of this test is to calibrate the LPRMs. LPRMs were calibrated at Test Conditions 3 and 5 to ensure LPRM readings are proportional to neutron flux.
Description:
The LPRM channels were calibratad to make the LPRM readings proportional to the neutron flux in the narrow narrow water gap at the chamber elevation. This calibration was performed in accordance with Procedure OPT.01.9.
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- O Hmnswick Steam Electric Plant Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 12 Accentance Criteria:
All acceptance criteria are established in procedure OPT.01.9,"LPRM Calibration".
Results:
Using site procedures, LPRMs were successfully calibrated at Test Condition 3. The results of that testing remained valid for Test Condition 5, so no further testing was required. All acceptance criteria were met.
6.2.5 Test 9 Average Power Range Monitor (APRM) Calibration Purame:
The purpose of this test is to calibrate the APRMs. Each APRM was adjusted, as necessary, per plant procedures to be consistent with core thermal power as determined by heat balance.
Description:
Each APRM channel reading was adjusted to be consistent with core thennal power as determined by the heat balance. This calibration was performed in accordance with Procedure 20P-09.
Acceptance Criteria:
Level I : APRM GAFs are s 1.0 Bysults:
APRM gain adjustments were performed at different power levels during the Power Uprate Startup Test Program. Each was completed satisfactorily, and no problems occurred durin, the tests.
6.2.6 Test 10 Process Computer i
Purpose:
The purpose of this test is to verify Core Perfonnance parameters monitored by the Process Computer accurately reflect Power Uprate operating conditions.
Description:
The plant computer group and reactor engineering group monitored the process computer and analyzed its perfonnance at Power Uprate Test Conditions 3,4 and 5 per Procedure OPT-50.0. The emphasis was placed on monitoring of the reactor core performance
. parameters.
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- lirunswick Steam Electric Plant Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 13 Agentance Criteria ;
All acceptance criteria are established in procedure OPT-50.0," Reactor Engineering Refueling Outage Testing".
Etantis 1 Procedure OPT-50.0 was performed satisfactorily ct Test Conditions 3,4 and 5. All ,
acceptance criteria were met. ,
1 6.2.7 Test 1I Reactor Core Isolation Cooling (RCIC) i
Purpose:
The purpose of this test is to verify operation of the RCIC system at the normal ogwrating reactor pressure condhions. The RCIC system was tested during startup of the unit per Technical Specification requirements at the new operating pressures. The testing also provided baseline data for future RCIC surveillance testing.
- 1)escription; To verify proper operation of RCIC following adjustments required by changes in system -
operational parameters, a cold quick start (cold quick start being defined as a rapid initiation of the system at ambient conditions) was demonstrated at uprated conditions.
Acceptance Criterlat All acceptance criteria are established in procedure OPT 10.1.1,"RCIC System Operability Test".
Results:
The RCIC pump surveillance procedure was performed. RCIC operability was verified at
%0 psig. The pump flow rate was 410 gpm at a pump discharge pressure of 1220 psig.
The cold quick start time to rated flow was acceptable. All acceptance criteria were satisfied. .
With reactor pressure at 960 psig, the RCIC tuning procedure was performed
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satisfactorily. The RCIO turbine did not trip; a rated flow of 435 gpm was achieved with a discharge pressure of 1320 psig, thus satisfying all Level 1 acceptance criteria. The control system tuning parameter checks also rret the acceptance criteria.
The dynamic response of the speed control loop was acceptable. All acceptance criteria
- were satisfied.
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lirunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 14 6.2.8 Test 12 liigh Pressure Coolant injection (llPCI)
Purpose:
The purpose of this test is to verify operation of the llPCI system throughout the range of reactor pressure conditions.
Description:
The !!PCI system was tested during startup of the unit per Technical Specification requirements at the new operating pressures. The testing provided baseline data for future llPCI surveillance testing.
Acceptance Crlierla:
All acceptance criteria are established in procedure OPT- 09.2,"IIPCI System Operability Test".
Results:
The llPCI pump surveillance procedure was perfonned at 945 psig. All acceptance criteria were satisfied as follows.
Parameter Acceptance Criteria Test Results Rated Flow 4250 ppm 4700 gpm Pump Discharge "ressure 1090 psig 1300 psig Response Time 560 seconds 39.63 seconds The cold quick start response of the speed control loop was acceptable, with no perceptible initial speed spike No speed requirements were exceeded. The dynamic response was acceptable, thereby satisfying all acceptance criteria.
The llPCI tuning procedure was perfonned satisfactorily No turbine trip or isolation occurred. The following acceptance criteria were satisfied.
Parameter Acceptance Criteria Test Results l Rated Flow 4250 gpm 4600 gpm Pump Discharge Pressure 1225 psid 1276 psid The transient start peak was well below the limit of 4510 rpm and subsequent peaks were well below the 4510 rpm limit. All acceptance criteria were met.
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Ilrunswick Steam Electric Plant Unit 2 !
Power Uprate Startup Test Report for Cycle 13 Page 15 6.2.9 Test 16 Core Performance
Purpose:
The purpose of this test is to evaluate core performance parameters to assure plant thermal limits are maintained during ascension to uprated conditions.
Description:
Core performance was monitored and thermal limits evaluated from 85% to 100% re.ver.
The data was part of the steady state operating data used for evaluations to project satisfactory operations at uprated power prior to exceeding the original 100% power rating.
Acceptance Crlieria:
The following thennal limits are s 1.000:
- 1. MFLPD (Maximum Fraction of Limiting Power Density)
- 2. MFLCPR (Maximum Fraction of Limiting Critical Power Ratio)
- 3. MAPRAT (Core Maximum Average Planar Linear lleat Generation Rate Fraction)
Results:
Thermal limits were continuously monitored during power ascension. The surveillance procedure was performed satisfectorily at each Test Condition, thus meeting all acceptance criteria. Results for Test Conditions 2 through 5 are as follows:
Test Condition MFLCPR MFLPD MAPRAT
(% Power )
2(8! '.'4) 0.830 0.650 0.834 2(87%)- 0.826 0.666 0.826 2(90%) 0.826 0.688 0.860 2(92%) 0.819 0.712 0.870 3(95%) 0.818 0.733 0.884 4(97%) 0.831 0.882 0.889 5(100%)' O.845 0.876 0.868
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Biunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 16 i i
6.2.10 Test 17 Steam Production ( Performance Difference) )
Porrune.
The purpose of this test is to demonstrate reactor steam production rate is satisfied.
Description:
For Power Uprate a Performance Difference Test was run to cor pare electrical production at the original (2436 MWt) conditions verses Power Uprve (2558 MWt) conditions.
Acceptance Criterlat None.
Results:
This test demonstrated that the actual electrical p>wer increase relative to the original rated value was approximately SE 6.2.11 Test 19 Pressure Regulator .
Purrune:
The purpose of this test is to.
- 1. Confirm that the recommended pressure control system tuning parameters provide acceptable performance t y analysis of the transients induced in the reactor pressure control system by means of pressure step input to the pressure regulators.
- 2. Demonstrate that affected plant parameters are within acceptable limits during pressure regulator induced transients.
- 3. Verify that variation in incremental regulation is within acceptable limits (linear).
- 4. Verify proper operation of the Steam Line Resonance Compensator (SLRC) cards.
This testing is being included to verify the stability of EllC pressure control system and its ability to respond to transients.
Description:
Modifications have been performed to the control valve Diode Function Generators (DFGs) that required testing to be included in the startup test plan. Prior to plant startup, adjustments were made to various pressure regulator settings per recommendations in GE SIL 589 Revision 1. Appropriate operation was confirmed through the various pressure regulator tests performed during the power ascension test program. Pressure setpoint step response testing was performed at 15% power to verify pressure regulator stability with
18 Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 17 the bypass valves controlling.
Control system stability with the control valves maintaining pressure was checked via response to pressure set point steps at 30%,60%, and s95% power. Satisfactory response to failure of the controlling regulator to the backup regulator was verified at 60% power. Acceptable variation in incremental regulation was demonstrated using data obtained in power increments from 30% to 100% power. 't.lonitoring of EllC fluid pressure perturbations was performed as well.
Acceptance Criteria:
EllC Pressure control shall prevent steady state limit cycles from producing variations in steam flow to the turbine larger than (+/-) 0.5% of rated total steam flow.
During the Pressure Setpoint step changes:
The peak neutron flux, peak heat flux, and peak vessel pressure will remain below the scram settings by the margins stated:
Neutron Flux ..... .... 7.5%
licat Flux........ .. ...... 5.0%
Reactor Pressure.....10.0 psig The time between the setpoint change and the occurrence of the pressure peak shall be 510 seconds.
The decay ratio must be s 0.25 for throttle pressure oscillatory response to the pressure regulator changes.
During the Fallare of the Controlling Pressure Regulater:
The peak neutron flux, peak heat flux, and peak vessel pressure will remain below the scram settings by the margins stated:
Neutron Flux........... 7.5%
ileat Flux................. 5.0%
Reactor Pressure ...10 psig The time between failure and the occurrence of the pressure peak shall be $10 seconds.
The acceptance criteria for variation in incrermntal regulation is contained in procedure 2SP-97-209," Power Uprate Turbine Incremental Regulation Testing".
Results:
Proper operation was confirmed through the various pressure regulator tests performed during the power ascension test program. The pressure regulator testing with bypass valves controlling and control system stability with control valves controlling was performed satisfactorily. The pressure regu!ator fail over test was performed satisfactorily. The system response to step changes at each powcr level was satisfactory.
No signs of divergence of oscillations occurred. Pressute response time and m' gms to
l Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 ,,
Pace 18 scram setpoints were adequate in all cases. Steady since steam flow variations were within allowable tolerance. All accep'mee criteria were satis 0ed.
6.2.12 Test 20 Feedwater System Parpose:
The purpose of this test is to demonstrate acceptable reactor water level control, and to evaluate and adjust feedwater controls at uprated conditions, as required.
Description:
Step changes in reactor water level were induced into the Digital Feedwater Control System (DFCS) while monitoring the system resporse. These step changes were performed in Test Conditions 3,4 and 5. The step level changes were performed in both single and three element control modes. Stability testing was performed in Test Condition I at 75% power to provide benchmark data for comparison with data at the higher power testing.
Acceptance Criteria:
All acceptance criteria are established in procedure 2SP-97-205," Unit 2 Power Uprate Digital Feedwater Control System Testing".
Results:
Response of the DFCS at uprated conditions has been validated through acceptable performance of the system to le"cl perturbations at various power levels. System response was rot oscillatory and showed no signs of divergence.. All Level I acceptance criteria, as defined in 2SP-97-205, were sntisfied. No adjustments to the system were necessary.
6.2.13 Test 21/33 Turbine Bypass Valves, Control Valves / Turbine Stop Valves
Purpose:
The purpose of this test is to demonstrate the ability if the pressure regulator to minimize disturbances to the reactor during abrupt changes in steam flow and to demonstrate that a bypass valve can be tested at rated power without causing a high flux scram.
Description:
The turbine control valves, bypass valves, and stop valves were functionally tested during startup to demonstrate adequate valve movement / pressure response and that surveillance can be performed satisfactorily on the valves at the conditions prescribed during normal operation. This testing is required due to the modifications to the DFG curves and to the main steam pressure transmitters.
Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 19 Acceptance Criteria:
Level 1 : 1. The selected turbine valve strokes fully.
- 2. The fast acting solenoids for the valves operate properly
- 3. Margin to the fligh Reactor Pressere setpoint is 215 psi.
_Results:
The turbine control valves, bypass valves and stop valves were functionally tested during this startup and demonstrated to have adequate valve movement / pressure response. This ensures that normal surveillance can be perfor.ned satisfactorily at the conditions presenbed F ;ing normal plant operation. All Level 1 acceptance criteria were satisfied.
6.2.14 Test 34 Recirculation System Flow Calibration ,
Purpose:
The purpose of this test was to perform a calibration of in installed recirculation system flow instrumentation. This testing will ensure secirculanon system flow inputs sre valid for all power levels.
Description:
The jet pump flow instrumentation was calibrated at recircuhtion How rates required to achieve 100% power. The process includes computer system adjustments necessary to ,
allow correct readouts of core now ar.d related ru 'rculation system parameters on the plant computer.
Acceptance Criteria; Level 1 : All acceptance criteria are established in procedure 017-50.5," Total Core Flow Calibration".
Results Core flow calibrations were performed satisfactorily. All Level I acceptance criteria were satis 0ed.
6.2.15 Test 35 Water Level Measurements Purrmst:
The purpose of this 5 to check wide-range and narrow-range vessel water level instrumentation throughout reactor startup to 100% power,
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i Brunswick Steam Electric Plant - Unit 2 ~,
Power Uprate Startup Test Report for Cycle '3 Page 20
Description:
Water level instruments were monitored throughout the startup by operations using existing procedures. Level instrumentation was recalibrated for Power Uprate conditions prior to startup. The reference leg backfill Dow rates were checked periodically and adjusted as necessary.
Acceptance Criteria:
Level 1 : All acceptance criteria are established in procedures 2SP-97-204," Unit 2 Power Uprate Data Collection", and 201-3.1," Control Operator Daily Surveillance Report".
Results:
All water level instrumentation and reference leg back0ll flow rates checked out satisfactorily. All Level 1 acceptance crit: ia were satisfied.
6.2.16 Test 36 Reactor Water Cleanup System Purimse:
The purpose of this test was to demonstrate the RWCU system opcrates properly over the full range of primary coolant temperatures and pressures.
Description:
Actual RWCU testing under power uprate conditions was performed prior to startup and the system performed satisfactorily. Therefore, RWCU testing was not required during plant startup. Ih, wever, operations monitored significant parameters during startup to assure proper operation.
Acceptance Criteria:
Level 1 : All acceptance criteria are established in procedure 2SP-97-204," Unit 2 Power Uprate Data Collection".
Results:
This test denionstrated that RWCU operated satisfactorily over the full range of primary coolant temperatures and pressures. All Level 1 acceptance criteria were satisfied.
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i Brunswick Steam Electric Plant - Unit 2 -
^ Power Uprate Startup Test Report for Cycle 13 - Page 21 6,3 OtherTests f
The result of the CRD Scram Time Test are included in the Brunswick Unit 2, Cycle 13 Neutronics Startup Report.
6.3.2 Shutdown Margin Test .
The results of the Shutdown Margin Test are included in the Brunswick Unit 2, Cycle 13 Neutronics Startup Report.- .
6.4 - License Condition Testing .
L 6.4.l~ CRD Cooling Water Flow Monitoring
Purpose:
.In accordance with the License Condition established for Power Uprate Operation, the -
CRD cooling water and drive water Cow rate was monitoird at the new operating ]
- pressure and temperature conditions to ensure adequate flow is available.
Description:
y The cooling water and drive water flow rate was monitored starting at 85% of rated - '
thermal power, The Control Operators used the indicators on H12-P603 to obtain tim actual flow, y
' Acceptance Criteria: ;
All acceptance criteria are established in procedure 2SP-97-204," Unit 2 Power Uprate Data Collection".
Results: i
~
. The operation of the CRD cooling water and drive water system was satisfactory under ?
~
Power Up; ate conditions.
6.4.2 : Reactor Recirculation Pump Motor Vibration Monitoring
Purpose:
~ . . . . .. .
1 In accordance with the License Condition established for Power Uprate_ Operation, the L Reactor Recirculation Pump Motor was monitored for in increase in vibration and noise .
. J at the new operating pressure and temperature conditions.
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Ilrunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 22
Description:
During power ascension from 85% to 100% power, the Control Operator monitored the annunciators for high reactor recirculation pump motor vibration. In addition the Auxiliary Operators monitored the Reactor Building for abnormal noise coming from the primary containment.
Acceptance Criteria:
All acceptance criteria are established in procedure 2SP-97-204," Unit 2 Power Uprate Data Collection".
Results:
The operation of the Reactor Recirculation Pump Motor was satisfactory under power uprate conditions.
Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 23 TABLE 1 UNIT 2 U/FSAR CilAPTER 14 TESTS 1
U/FSAR TEST NO. TEST REQUIRED FOR POWER UPRATE I CilEMICAL AND YES RADIOCilEMICAL 2 RADIATION MEASUREMENTS YES 3 FUEL LOADING NO 4 FULL CORE SillTFDOWN NO MARGIN
$ CONTROL ROD DRIVE YES 6 SRM PERFORMANCE AND NO CONTP.0L ROD SEQUENCE 7 IRM PERFORMANCE NO 8 LOCAL POWER RANGE YES MONITOR 9 AVERAGE POWER RANGE YES J MONITOR 10 PROCESS COMPUTER YES 11 REACTOR CORE ISOLATION YES COOLING 12 111G11 PRESSURE COOLANT YES INJECTION 13 SELECTED PROCESS NO TEMPERATURES 14 SYSMt EXPANEION NO 15 CORE POWER DISTRIPUTION NO 16 CORE PERFORMANCE YES 17 STEAM PRODUCTION YES
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-18 FLUX RESPONSE TO RODS NO 19 PRESSURE REGULATOR YES l
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- Brunswick Steam Electric Plant - Unit 2
- Power Uprate Startup Test Report for Cycle 13 Page 24 U/FSAR TEST NO. TEST REQUIRED FOR POWER >
UPRATE i 20 FEEDWATER SYSTFM YES 21 TURBINE BYPASS VALVES, YES CONTROL VALVES 22 '
MAIN STEAM IFOLATION NO VALNB 23 RELIEF VALVES NO 24 TURBINE STOP VALVE TRIP NO 25 GENERA' TOR LOAD NO REJECTION
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26 FLOW CONTROL NO ,
27 RECIRCULATION SYSTEM NO 28 LOSS OF TURBINE NO GENERATOR AND OFFSITE POWER 29 RECIRCULATION MO SET NO SPEED CONTROL 30 VIBR ATION MONITORING . NO 3i SilUTDOWN FROM OlJi' SIDE NO Tile CONTROL ROOM
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32 RESIDUAL llEAT REMOVAL NO (RilR) SYSTEM
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33- TURBINE STOP VALVE YES SURVEILLANCE 34 RECIRCULATLION SYSTEM YES FLOW CALIBRATION 35 WATER LEVEL YES MEASUREMENTS 36 REACTOR WATER CLEANUP YES i
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,, 6 Brunswick Steam Electric Plant - Unit 2 +
Power Uprate Startup Test Report for Cycle 13 Page 25 ,
TABLE 2 ,
TEST CONDITIONS ,
TEST CONDITION PERCENT POWER 1 0 -85
'2 85 - 95 3 95 4 97 5 100 d
l';) 1 L 13f* - - . - - , , - . _ , - - .. . - . , - .- , . . . . - . . . - . . - -
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Brunswick Steam Electric Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Page 26 TABLE 3 TESTS PERFORMED FOR POWER UPRATE TEST CONDITION I 4 U/FSAR TEST 1 2 3 ;
5 TEST NO.
1 CilEh11 CAL AND X X X RADIOCllEh11 CAL 2 RADIATION h1EASUREhtENTS X X 5 CONTROL ROD DRIVE X X 8 LPRh1 CALIBRATION X X 9 APRhi CALIBRATION X X 10 PROCESS COh1PUTER X X X 11 RCIC X 12 IIITI X 16 CORE PERFORh1ANCE X X X X 17 STEAh! PRODUCTION X X 19 PRESSURE REGULATOR X X X X 20 FEEDWATER SYSTEh! X X X X 21 TURBINE BYPASS / CONTROL X X VALVE 33 TURBINE STOP VALVE X X 34 RECIRC, SYSTEh! FLOW X CALIBRATION 35 WATER LEVEL X X h1EASUREh1ENTS 36 RWCU X X X X X
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