ML20148E944
| ML20148E944 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/29/1997 |
| From: | Beller L, Helme R, Lenoir V CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20148E941 | List: |
| References | |
| NUDOCS 9706030321 | |
| Download: ML20148E944 (28) | |
Text
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HRUNSWICK STEAM ELECTRIC PLANT UNITI POWER UPRATE STARTUP TEST REPORT FOR 1
CYCLE 11 ,
Prepared by: % ! M Vincent P.15eNo .
3 Leonard R.'Beller Approved by: ' be Robert E. Helme Power Uprate Project Manager 9706030321 970529 DR ADOCK0500g5
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i 1 1 Brunswick Steam Electric Plant - Unit I ;
i Power Uprate Startup Test Report
{
i For Cycle 11
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1-4 Table of Contents 4~-
1 Section P_ age d
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- . 1.0 Ex ecutive S ummary.. . .. . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . .... . ... . .. .. . .. . . . .. . .. . . .......... .. 1
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2.0 Purpose.............................................................................................. 2 i
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i 3.0 Program Desc ription. . . . .. . . . . . ... ... . . . . ... .. . .. . . . . .. . .. ... . . .. . . ... . .... . . ... .. . .. . . ... . . . . . . . 2 8
4.0 Acceptance Criteria.. ...................... . ....... ... ..................................... 3 i 1
5.0 Power Uprate Startup Test Program Summary..................... ... .......... .... 3
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6.0 . Testi n g Req uirements.. . . . . . . . ... . . . .. .. . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . .... . .. 4. '!
6.1 UFSAR Chapter 14 Tests Not Required for Power Uprate.. ......... 5 1
i 6.2 UFSAR Chapter 14 Tests Required for Power Uprate....... ............ 9 !
l 6.3 OtherTests............................................................................... 21 1 6.4 License Condition Testing................... ....................... ................... 21 Tables 1
'1 Unit 1 UFSAR Chapter 14 Tests.......... ... ...................... ....... .. ....... ...... 23 l i
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2 Te s t C o n d i t i ons. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .25
'3- Tests Performed for Power Uprate.................. . ....... . ... ......................... 26 i
Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page1 1.0 EXECUTIVE
SUMMARY
The Brunswick Unit 1 Power Uprate Startup Test Report is submitted to the Nuclear Regulatory Commission (NRC) in accordance with Unit 1 Technical Specifications. The report summarizes the star:up testing performed on Unit 1 following implementation of power uprate during the eleventh refueling outage. Power Uprate was implemented in accordance with Amendment No.183 of Facility Operating License No. DPR-71.
The result of Power Uprate is an increase in reactor thermal power equal to 5% of the original rated thermal power. All testing specified in Chapter 14 of the UFSAR was i addressed and evaluated for applicability to this increased licensed power rating.
The Reactor Mode Switch was placed in the Startup position on November 5,1996. The final synchronization to the grid was performed on November 7, marking the official end to the Unit I refueling outage. The new 100% power was first achieved on April 16, 1997. All required power uprate startup tests were completed by April 18,1997. 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-Hydraulic Control (EHC) - Pressure Regulation, Feedwater, Reactor Core Isolation Cooling (RCIC), and High Pressure Coolant Injection (HPCI). All systems performed in a stable manner during both plant startup and transient testing. The unit is operating satisfactorily at power uprated conditions.
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Brunswick Steam Electric Plant - Unit 1 I Power Uprate Startup Test Report for Cycle 11 Page 2 4
2.0 PURPOSE l The Brunswick Unit 1 Power Uprate Startup Test Report summarizes the testmg performed on Unit 1 following the implementation of power uprate which resulted in an l increase in reactor thermal power equal to 5% of the original rated thermal power. Each i
~ test performed for power uprate is described in Section 6.0. This report is submitted in j accordance with the requirements of the Unit 1 Technical Specifications. l t
3.0 PROGRAM DESCRIPTION The power uprate startup testing requirements were developed primarily from the review of the Unit 1 Technical Specifications, Chapter 14 of the UFSAR (Table 1), the General Electric (GE) Power Uprate Safety Analysis Report for the Brunswick Steam Electric Plant Units 1 and 2, and the GE Uprate Test Program Recommendations. The testing was conducted following the Unit I eleventh 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. i The majority of testing falls within the following categories:
- 1. Verification of the control systems (i.e., Feedwater and EHC-Pressure Regulation) ,
are stable at power uprate conditions.
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- 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. l l
Table 2 presents the Test Conditions at which startup testing was performed. Reactor !
core flow could be any flow within the safe operating region of the power / flow map that will produce the required power level. Testing at a given Test Condition was completed prior to proceeding to the subsequent Test Condition. Prior to increasing power above the old rated thermal power level of 2436 MWt, 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 of Site Operations.
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Brunswick Steam Electric Plant - Unit I !
- Power Uprate Startup Test Report for Cycle 11 Page 3 l 4.0 ACCEPTANCE CRITERIA l Acceptance Criteria for Power Uprate testing are contained in the individual procedures !
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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 t I- placed in a satisfactory hold condition, until a resolution is made.
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5.0 POWER UPRATE STARTUP TEST PROGRAM
SUMMARY
i The test program began when the Mode Switch was placed in Startup on November 5, 1996 and ended with all required Power Uprate Startup Tests completed on April 18, ;
, 1997. The unit was synchronized to the grid on November 7,1996, marking the official end to the Unit 1 eleventh refueling outage. CP&L limited operation to 95% power pending the resolution of various items. The items were resolved and the approval to ;
. resume power ascension testing was granted on March I8,1997. Not associated with {
j power uprate, an ultrasonic feedwater flow test was performed to determine the calibration accuracy of the feedwater flow transmitters. The results of the ultrasonic test indicated the transmitters were potentially non-conservative by approximately 1.6%. The decision was made to reduce power by 2% and recalibrate the flow transmitters based on l
? the results of the ultrasonic test prior to resuming the power ascension testing above 95% j thermal power. For a detailed discussion of this event see Licensee Event Report (LER) j 1-97-005. The transmitters were recalibrated and power ascension testing was resumed i on April 16,1997. The new uprated 100% power (2558MWt) was first achieved on April 16,1997.
The unit is operating satisfactorily at the uprated conditions. Prior to the sign-off of the final start-up test hold point, two conditions were noted. Turbine Control Valve No. 3 experienced a problem that prevented the valve from operating as designed. It was determined that the printed circuit card for the No. 3 Diode Function Generator had a failed component. The card was replaced and the valve responded satistactorily. The second problem encountered dealt with what is believed to be a pre-exi' sting fuel perforation. Once 100% power operation was achieved, the perforation became more pronounced. Adjacent control roos were inserted to successfully suppress the suspected bundle. No unanticipated online adjustments were required to control systems for the following: EHC-Pressure Regulation, Feedwater, RCIC, or HPCI Systems. All systems performed in a stable manner.
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4 Brunswick Steam Electric Plant - Unit 1 ;
Power Uprate Startup Test Report for Cycle 11 Page 4 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 eleventh 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 ;
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6.0 TESTING REQUIREMENTS l
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, l titles, and format are consistent with the UFSAR.
Section 6.1 identifies each Chapter 14 test not required to be performed for Power Uprate.
The purpose of the test and rationale, for exempting the test from the Power Uprate program are discussed.
Section 6.2 identifies each test required to be performed 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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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 5 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 performed during refuel outages in accordance with site procedures and Power ,
Uprate has no affect on the evolution; therefore, no testing is required for Power Uprate. J 6.1.2 Test 4 Full Core Shutdown Margin l
The purpose of the Shutdown Margin test is to demonstrate that throughout the fuel cycle the reactor will be suberitical with the analytically determined 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. However, Shutdown Margin Demonstrations are required during a startup following core alterations and were included in the initial start-up report submitted to the NRC under cover letter BSEP 97-0052, dated February 5,1997.
6.1.3 Test 6 SRM Performance and Control Rod Sequence i I
The purpose of this test is to demonstrate that the Source Range Monitor (SRM) l instrumentation, and rod withdrawal sequences provide adequate information to the I 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 purpose 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
l Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 6 pressure and to provide assurance that the measured bottom head drain temperature I cerresponds to bottorn head coolant temperature during normal operations. Temperature stratification limits are defined in the Technical Specifications and controlled by plant procedures during startup independent of Power Uprate startup 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 the 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 (TlP) 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; 4
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 l to the movement of control rods; therefore, no testing is required. l 6.1.9 Test 20 Feedwater System The purpose of this series of tests is to demonstrate acceptable reactor water level control, j to evaluate and adjust feedwater controls, to demonstrate the capability of the automatic l 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 these 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.
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i Brunswick Steam Electric Plant - Unit I !
Power Uprate Startup Test Report for Cycle 11 Page 7 I l
6.1.10 Test 22 Main Steam Isolation Valves
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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 MSlVs and following closure of one valve, and to detemline isolation !
valve closure time. Large transient testing performed at high power during the initial I 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. MSlVs will continue to be tested by plant procedures during normal operation; therefore, further testing is not required.
6.1.11 Test 23 ReliefValves The purpose of this test is to verify proper op; ration of the dual purpose safety relief valves (SRV), to determine their capacity, and to verify proper reseating following operation. Power Uprate will 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 determine the response of the reactor to a fast closure of turbine-generator stop valves and to evaluate the response of bypass valves, relief valves, and reactor protection system. The purpose of the Generator Load Reject test is to demonstrate the ability of the unit to reject design load without trip and to demonstrate reactor response is within expected limits. Large transient testing performed v 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; therefore, further testing is not required
- 6.1.13 Test 26 Flow Control i l
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 j plant is established. Power Uprate does not significantly affect the recirculation flow i control system, or core flow limits; therefore, the recirculation flow control test is not I required for Power Uprate Startup testing.
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report fbr Cycle 11 Page 8 6.1.14 Test 27 Recirculation System The purpose of this test is to determine transient response and steady-state conditions 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 i for Power Uprate testing. ;
6.1.15 Test 28 Loss of Turbine Generator Offsite Power The purpose of this test is to demonstrate proper performance of the 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 of this test is to determine the as-built characteristics of the recirculation
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control system. Power Uprate does not affect the recirculation flow loop and is therefore not included in the Power Uprate Startup Test Plan. I 6.1.17 Test 30 Vibration Monitoring The purpose of this test is to determine vibration characteristics of the reactor internals.
A comprehensive review was performed by GE for the affects ofincrease power and pressure conditions on the reactor vessel internals. This review showed a continued 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 shutdown from outside the control room; therefore, this te.st was not added to the Power Uprate Startup Test Plan.
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle i1 Page 9 6.1.19 Test 32 Residual Heat Removal (RHR) System The purpose of this test is to demonstrate the ability of the RIIR 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 RIIR 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 testing 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.
6.2 UFSAR Chapter 14, Table 14.2.1-1 Tests Required for Power Uprate 6.2.1 Test 1 Chemical and Radiochemical
Purpose:
The purpose of this test is to maintain control and knowledge of the quality of feedwater and reactor coolant chemistry. With Unit 1 increasing rated thermal power to 2558 MWt, it is desirable to track chemistry parameters rad evaluate the results for uprated power.
Descrintion:
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 OAI - 81 was performed satisfactorily in Test Conditions 3,4 and 5. All !
acceptance criteria was met.
Chemistry Results
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Parameter Test Condition 3 Test Condition 4 Test Condition 5' Conductivity 0.083 0.083 0.083
( mho/cm)
Dose Equivalent 6.17E-3 6.59E-3 7.50E-3 1-131 ( Ci/mL)
SJAE 297 384 422 (uCi/sec)
Note 1 Represents final reactor chemistry following suppression of fuel perforation discussed in Section 5 0
mum - m. _ ..m_ _ , _ , .~,_...m a m ..,_,mm._..a +. _.m...
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' Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 10
- 6.2.2 Test 2 Radiation Measurements
Purpose:
The purpose of this test is to measure radiation levels at selected locations
- and power levels to ensure compliance with 10 CFR 20 during plant operations.
Description:
Radiation levels were measured at various locations in the plant at uprated power levels during Test Conditions 4 and 5.
Acceptance Criteria: ,
Level 1: 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.
Resultst Radiation surveys were conducted at uprated power levels in Test Conditions 4 and 5. No postings were 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 primary 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 I established as a license condition for approval of the Power Uprate hcense I
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 ISP-96-106,
" Unit 1 Power Uprate Data Collection".
Results: All cooling water flow and drive water flow data taken from this test was found acceptable. 3
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 11 6.2.4 Test 8 Local Power Range Monitor (LPRM) Calibration l
Purpose:
l 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.
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Description:
The LPRM channels were calibrated to make the LPRM readings l 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.
Acceptance Criteria: All acceptance criteria are established in procedure OPT.01.9, "LPRM Calibration" Results: Using site procedures, LPRMs were successfully calibrated at Test Conditions 3 and 5. Average LPRM Gain Adjustment Factors (GAFs)for all operable LPRM channels were within specified limits.
6.2.5 Test 9 Average Power Range Monitor (APRM) Calibration
Purpose:
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 thermal power as determined by the heat balance. This calibration was performed in accordance with Procedure IOP-09.
Acceptance Criteria:
Level 1: APRM GAFs are s 1.0 Results: APRM gain adjustments were performed at different power levels during the Power Uprate Startup Test Program. Each was completed satisfactorily, and no problems occurred during the tests.
6.2.6 Test 10 Process Computer
Purpose:
The purpose of this test is to verify Core Performance parameters monitored by the Process Computer accurately reflect Power Uprate operating conditions.
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 12
Description:
The plant computer group and reactor engineering group monitored the process computer and analyzed its performance 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.
Acceptance Criteria: All acceptance criteria are established in procedure OPT-50.0,
" Reactor Engineering Refueling Outage Testing".
Results: Procedure OPT-50.0 was performed satisfactorily at Test Conditions 3,4 and 5. All acceptance criteria were met.
6.2.7 Test 11 Reactor Core Isolation Cooling (RCIC)
Purnose: The purpose of this test is to verify operation of the RCIC system at the normal operating reactor pressure conditions. 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.
Description:
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.
4 Acceptance Criteria: All acceptance criteria are established in procedure OPT- 10.1.1, "RCIC System Operability Test".
Results:
The RCIC pump surveillance procedure was performed satisfactorily. RCIC operability was verified at 970 psig. The pump flow rate was 400 gpm at a turbine speed of 4600 rpm and a pump discharge pressure of 1125 psig. The time to rated flow was acceptable.
All acceptance criteria were satisfied.
With reactor pressure at 970 psig, the RCIC pump surveillance procedure was performed satisfactorily. The RCIC turbine did not trip; a rated flow of 450 gpm was achieved with a discharge pressure of 1200 psig, thus satisfying all Level 1 acceptance criteria. The control system tuning parameter checks also met the acceptance criteria.
The RCIC pump surveillance procedure was performed satisfactorily at uprated pressure.
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- Brunswick Steam Electric Plant - Unit 1 Power Uprate Stanup Test Report for Cycle 11 Page 13 A Cold Quick Start was performed. The RCIC pump flow was 450 gpm at a pressure of 1200 psig. The response time to rated flow was acceptable, with no perceptible initial speed spike. No tuning was needed; the system ran smoothly.
The dynamic response of the speed control loop was acceptable. All acceptance criteria were satisfied.
i 6.2.8 Test 12 High Pressure Coolant Injection (HPCI) 1 l
Purpose:
The purpose of this test is to verify operation of the HPCI system j throughout the range of reactor pressure conditions. ;
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Description:
The HPCI system was tested during startup of the unit per Technical Specification requirements at the new operating pressures. The testing provided baseline data for future HPCI surveillance testing.
Acceptance Criteria: All acceptance criteria are established in procedure OPT- 09.2, "HPCI System Operability Test".
Results: 1 The HPCI pump surveillance procedure was performed satisfactorily. A pump flow rate j of 4400 gpm was achieved. Turbine speed was 4100 rpm; the turbine did not trip. All acceptance criteria were satisfied.
The HPCI pump surveillance was completed satisfactorily at 971 psig. The following acceptance criteria were met.
IIPCI pump flow was 4400 gpm at a pressure of 1325 psid. The dynamic response of the speed control loop was acceptable, with no perceptible initial speed spike.
r-Parameter Acceptance Criteria Test Results Rated Flow 4250 grm 4400 gpm Pump Discharge Pressure 1226 psid 1325 psid Response Time' s60 seconds 35.02 seconds Note 1: The response time test was performed to fulfill the Technical Specification Surveillance Requirement on 1/17/97, not during the original power uprate startup test.
Brunswick Steam Electric Plant - Unit i Power Uprate Startup Test Report for Cycle 11 Page 14 No speed requirements were exceeded. The speed and flow control loops did not require any adjustments. The dynamic response was acceptable, thereby satisfying all acceptance criteria.
The HPCI pump surveillance was perfomied satisfactorily at 100% uprated power. A !
Cold Quick Start was performed in conjunction with a stability (tuning) check. No :
turbine trip or isolation occurred. The following acceptance criteria were satisfied. j Parameter Acceptance Criteria Test Results !
Rated Flow 4250 gpm 4550 gpm Pump Discharge Pressure 1090 psig 1180 psig 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.
6.2.9 Test 16 Core Performance l
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%
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to 100% power. The data was part of the steady 5 tate operating data used !
for evaluations to project satisfactory operations at uprated power prior to j exceeding the original 100% power rating. j Acceptance Criteria:
The following thermal 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 Heat Generation Rate Fraction)
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- Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 15 Results: Thermal limits were continuously monitored during power ascension. The surveillance procedure was perfr,rmed satisfactorily at each Test Condition, thus meeting all acceptance criteria. Results fcr Test Conditions 2 through 5 are as follows:
Test Condition MF1 ' MFLPD MAPRAT
(% Power) 2(85%) 0.839 0.710 0.802 2(87%) 0.832 0.746 0.832 ,
2(90%) 0.830 0.772 0.839 2(92%) 0.826 0.791 0.848 3(95%) 0.825 0.816 0.864 4(_97%) 0.910 0.831 0.911 5(100 %) 0.907 0.858 0.927 6.2.10 Test liSteam Production ( Performance Difference)
Purpose:
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 compare electrical production at the old (2436 MWt) conditions verses Power
- Uprate (2558 MWt) conditions.
Acceptance Criteria: None.
Results: This test demonstrated that the actual electrical power increase relative to the original rated value was approximately 5%. i l
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 16 6.2.11 Test 19 Pressure Regulator
Purpose:
The purpose of this test is to:
- 1. Confirm that the recommended pressure control system tuning parameters provide acceptable performance by analycis 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 li.uits ,
during pressure regulator-induced transients.
- 3. Verify that variation in incremental regulation is within acceptable limits
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- 4. Verify proper operation of the Steam Line Resonance Compensator (SLRC) cards. This testing is being included to verify the stability of EllC pressum control system and its ability to respond to transients.
Description:
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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 press. ire regulator stability with 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 97% 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 j power increments from 30% to 100% power. Monitoring of EllC pressure perturbations was performed as well.
I Arcentance CritrN Level 1 - EHC Prenure control shall prevent steady state limit cycles from producing variations in steam flow to the turbine larger than (+/-) 0.5% of rated total steam ilew.
Brunswick Steam Electric Plant - Unit 1 i Power Uprate Startup Test Report for Cycle 11 Page 17 j During the Pressure Setpoint step changes:
The peak neutron flux, peak heat flux, and peak vessel pressure will remain below the 1 scram set ings by the margins stated:
Neutron Flux . .. .. .. 7.5%
Heat Flux.. . .. . ... . 5.0% i Reactor Pressure.....10.0 psig The time between the setpoint change and the occurrence of the pressure peak shall be I s 10 seconds.
The decay ratio must be 5 0.25 for throttle pressure oscillatory response to the pressure !
regulator changes.
During the Failure of the Controlling Pressure Regulator:
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%
Heat Flux...... ........ . 5.0%
l Reactor Pressure ...10 psig The time between failure and the occurrence of the pressure peak shall be 510 seconds.
The acceptance citeria for variation in incremental regulation is wntained in procedure ISP-96-111,"Pev r 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 i
performed satisfactorily. The pressure regulator fail over test was performed satisfactorily. The system response to step ch%es at each power level was satisfactory.
No signs df divergence of oscillations occurred. Pressure response time and margins to scram setpoints were adequate in all cases. Steady state steam flow variations were l
within allowable tolerance. All Level 1 acceptance criteria were satisfied.
! 6.2.12 Test 20 Feedwater System l
l l'
Purpose:
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 1;igital Feedwater Control System (DFCS) while monitoring the system response. These step changes were performed in Test Conditions 3,4 and 5. The step level changes were
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. i l Brunswick Steam Electric Plant - Unit 1 i Power Uprate Startup Test Report for Cycle 11 Page 18
_ performed in both single and three element control modes. Stability testing was l performed in Test Condition 1 at 75% power to provide benchmark data for comparison !
with data at the higher power testing. ,
f l Acceptance Criteria: ' All acceptance criteria are established in procedure ISP-96-104, ;
" Unit 1 Power Urrate Digital Feedwater Control System Testing". i L i
- Results
Response of the DFCS at uprated conditions has been validated through acceptable ;
performance of the system to level perturbations at various power levels. System i response was not oscillatory and showed no signs of divergence. All Level 1 acceptance !
criteria, as defined in ISP-96-106, were atisfied.
o No adjustments to the system were necessary, ;
i
- 6.2.13 Test 21/33 Turbine Bypass Valves, Control Valves / Turbine Stop Valves i 1
- Purpose.
The purpose of this test is to demonstrate the ability of the pressure regulator to minimize !
5 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 i
- startup to demonstrate adequate valve movement / pressure response and that surveillance can be performed satisfactorily on the valves at the conditions prescribed during normal i operation. This testing is required due to the modifications to the DFG curves and to the !
r main steam pressure transmitters. '
L !
< Acceptance Criteria:
Level 1: 1. The selected turbine valve strokes fully. l I
- 2. The fast-acting solenoids for the valves operate properly l 1
- 3. Margin to the High Reactor Pressure setpoint is > 15 psi.
1 i
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 19 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 performed satisfactorily at the conditions ,
prescribed during 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 the installed recirculation system .
flow instrumentation. This testing will ensure recirculation system flow inputs are valid for all power levels. l
Description:
The jet pump flow instrumentation was calibrated at recirculation flow rates required to achieve 100% power. The process includes computer system adjustments necessary to allow correct readouts of core flow and related recirculation system parameters on the ,
plant computer.
Acceptance Criteria:
Level 1: All acceptance criteria are established in procedure OPT-50.5, " Total Core Flow Calibration".
Results: Core flow calibrations were performed satisfactorily. All Level 1 acceptance criteria were satisfied.
l 6' Test 35 Water Level Measurements j Purnose:
l The purpose of this test is to check wide-range and narrow-range vessel water level
! instrumentation throughout reactor startup to 100% power.
l l
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 flow rates were checked periodically and adjusted as necessary.
Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 20 Acceptance Criteria:
Level 1: All acceptance criteria are established in procedures 1 SP-96-106, " Unit 1 Power Uprate Data Collection", and 101-3.1," Control Operator Daily Surveillance Report".
Results: ,
All water level instrumentation and reference leg backfill flow rates checked out +
satisfactorily. All Level 1 acceptance criteria were satisfied. ;
6.2.16 Test 36 Reactor Water Cleanup System
Purpose:
l The purpose of this test was to demonstrate the RWCU system operates 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 i '
j plant startup. Ilowever, operations monitored significant parameters during stanup to assure proper operation.
Acceptance Criteria:
1 Level 1: All acceptance criteria are established in procedure ISP-96-106," Unit 1 l l Power Uprate Data Collection". l l l Results:
j This test demonstrated that RWCU operated satisfactorily over the full range of pnmary l l coolant temperatures and pressures. All Level 1 acceptance criteria were satisfied. l l
i
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l Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Pag.e 21 6.3 Other Tests 6.3.1 CRD Scram Timing The result of the CRD Scram Time Test was reported in the initial start-up report submitted to the NRC under cover letter BSEP 97-0052, dated February 5,1997.
6.3.2 Shutdown Margin Test )
i I The results of the Shutdown Margin Test was reported in the initial start-up report !
subinitted to the NRC under cover letter BSEP 97-0052, dated February 5.1997. !
l 6.4 License Condition Testing
! - 6.4.1 CRD Cooling Water Flow Monitoring L
Purpose:
In accordance with the License Condition established for Power Uprate Operation, the CRD cooling water and drive water flow rate was monitored at the new operating '
pressure and temperature conditions to ensure adequate flow is available. . ;
I
Description:
. 1 The cooling water and drive water flow rate was monitored starting at 85% of rated l thermal power. The Control Operators used the indicators on H12-P603 to obtain the actual flow. j AcceDiance Criteria j All acceptance criteria are established in procedure ISP-96-106," Unit 1 Power Uprate j Data Collection",
j l l Results- !
- The operation of the CRD cooling water and drive water system was satisfactory under i
- Power Uprate conditions.
6.4.2 Reactor Recirculation Pump Motor Vibration Monitoring 4
Purpose:
- Ja accordance with the License Condition established for Power Uprate Operation, the
- Reactor Recirculation Pump Motor was monitored fer in increase in vibration and noise
. at the new operating pressure and temperature conditions.
- . . - . . . - . . . - . - . . . . . . - . ~ . . . - . _ ~
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Brunswick Steam Electric Plant - Unit 1 ,
l Power Uprate Startup Test Report for Cycle 11 Page 22 j
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 - !
i.
i Acceptance Criteria: !
' All acceptance criteria are established in procedure ISP-96-106," Unit 1 Power Uprate l l Data Collection". ~l Results: ;
The operation of the Reactor Recirculation Pump Motor was satisfactory under power [
uprate conditions, j I
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Brunswick Steam Electric Plant - Ucit 1 j Power Uprate Startup Test Report for Cycle 11 Page 23 .;
s l TABLEl i UNIT I U/FSAR CHAPTER 14 TESTS !
i U/FSAR TEST NO. TEST REQUIRED FOR POWER j UPRATE :
-1 CHEMICAL AND YES l RADIOCHEMICAL i 2 RADIATION MEASUREMENTS YES 3~ FUEL LOADING NO 4 FULL CORE SHUTDOWN NO MARGIN l 5 CONTROL ROD DRIVE . YES ;
6 SRM PERFORMANCE AND NO ;
- CONTROL ROD SEQUENCE ,
i .- !
7 IRM PERFORMANCE NO j 8 LOCAL POWER RANGE YES MONITOR - ,
9 AVERAGE POWER RANGE YES i MONITOR
- 10 PROCESS COMPUTER YES ;
11' REACTOR CORE ISOLATION YES l COOLING l t
.12- HIGH PRESSURE COOLANT YES j INJECTION i
!- '13 SELECTED PROCESS NO TEMPERATURES l 14 SYSTEM EXPANSION NO 15 CORE POWER DISTRIBUTION NO l
, I 16 CORE PERFORMANCE YES i 17 STEAM PRODUCTION YES )
i 18 FLUX RESPONSE TO RODS . NO l i
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Brunswick Steam Electric Plant - Unit 1 Power Uprate Startup Test Report for Cycle 11 Page 24 I U/FSAR TEST NO. TEST REQUIRED FOR POWER UPRATE 19 PRESSURE REGULATOR YES 20 FEEDWATER SYSTEM YES 21 TURBINE BYPASS VALVES, YES '
CONTROL VALVES ;
22 MAIN STEAM ISOLATION NO VALVE 23 RELIEF VALVES NO 24 TURBINE STOP VALVE TRIP NO 25 GENERATOR LOAD NO REJECTION 26 FLOW CONTROL NO 27 RECIRCULATION SYSTEM NO 28 LOSS OF TURBINE NO GENERATOR AND OFFSITE POWER l
29 RECIRCULATION MG SET NO SPEED CONTROL 30 V!BRATION MONITORING NO l
31 SHUTDOWN FROM OUTSIDE NO Tile CONTROL ROOM 32 RESIDUAL llEAT REMOVAL NO l (RifR) SYSTEM l
33 TURBINE STOP VALVE YES SURVElLLANCE 'i i
1 l 34 RECIRCULATLION SYSTEM YES FLOW CAllBRATION 35 WATER LEVEL YES MEASUREMENTS 36 REACTOR WATER CLEANUP YES 1
et / e. ;
t Brunswick Steam Electric Plant - Unit 1 -
Power Uprate Startup Test Report for Cycle 11 Page 25 [
TABLE 2 TEST CONDITIONS 7 TEST CONDITION PERCENT POWER '
v I
1- 0-85 !
t 2 85 - 95 3 95 t 1'
4 97 5 100
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$' $ %. d Brunswick Steam Electric Plant - Unit 1
. Power Uprate Startup Test Report for Cycle 11 Page 26 TABLE 3 TESTS PERFORMED FOR POWER UPRATF TEST CONDITION U/FSAR TEST <1 1 2 3 4 5 TEST NO. l 1 CHEMICAL AND X X X RADIOCHEMICAL ;
2 RADIATION MEASUREMENTS X X l 1
- 5. CONTROL ROD DRIVE X X l 8 LPRM CAllBRATION X X {
9 APRM CAllBRATION X X j t
10 PROCESS COMPUTER X 'X X {
~16 CORE PERFORMANCE X X X X- i 17 STEAM PRODUCTION X X 19 PRESSUf)E REGULATOR X X X X 20 FEEDWATER SYSTEM X X X X 21 TURBINE BYPASS / CONTROL X X l VALVE i
33 TURBINE STOP VALVE X X l 1
34 RECIRC. SYSTEM FLOW X CALIBPATION 35 . WATER LEVEL : X X MEASUREMENTS 36 RWCU X X X X X
_. __ _ _ _ .